Publications and reports related to Serpent development

Aufiero, M., Cammi, A., Fiorina, C., Leppänen, J., Luzzi, L. and Ricotti, M. (2013a) "An extended version of the Serpent-2 code to investigate fuel burn-up and core material evolution of the molten salt fast reactor." J. Nucl. Mat., 441 (2013) 473-486.
Aufiero, M., Brovchenko, M., Cammi, A., Clifford, I., Geoffroy, O., Heuer, D., Laureau, A., Losa, M., Luzzi, L., Merle-Lucotte, E., Ricotti, M. E. and Rouch, H. (2014) "Calculating the effective delayed neutron fraction in the molten salt fast reactor: Analytical, deterministic and Monte Carlo approaches." Ann. Nucl. Energy, 65 (2014) 78-90.
Aufiero, M., Bidaud, A., Hursin, M., Leppänen, J., Palmiotti, G., Pelloni, S. and Rubiolo, P. (2015) "A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT." Ann. Nucl. Energy, 85 (2015) 245-258.
Aufiero, M. and Fratoni, M. (2016d) "Testing Advanced Methods for Sensitivity/Uncertainty Analysis in the Monte Carlo Code Serpent." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Aufiero, M., Palmiotti, G., Salvatores, M. and Sen, S. (2016e) "Coupled reactors analysis: New needs and advances using Monte Carlo methodology." Ann. Nucl. Energy, 98 (2016) 218-225.
Aufiero, M., Martin, M. and Fratoni, M. (2016f) "XGPT: Extending Monte Carlo Generalized Perturbation Theory capabilities to continuous-energy sensitivity functions." Ann. Nucl. Energy, 96 (2016) 295-306.
Aufiero, M., Qiu, Y. and Fratoni, M.(2016g) "The Iterated Fission Matrix Method." Trans. Am. Nucl. Soc., 115 (2016) 567-570.
Dorval, E. (2013) "A new method for the calculation of diffusion coefficients with Monte Carlo." In proc. SNA + MC 2013, Paris, France, Oct. 27-31, 2013.
Dorval, E. and Leppänen, J. (2015) "Monte Carlo current-based diffusion coefficients: Application to few-group constants generation in Serpent." Ann. Nucl. Energy, 78 (2015) 104-116.
Dorval, E. (2016a) "Directional diffusion coefficients and leakage-corrected discontinuity factors: Implementation in Serpent and tests." Ann. Nucl. Energy, 87 (2016) 101-112.
Dorval, E. (2016b) "A comparison of Monte Carlo methods for neutron leakage at assembly level." Ann. Nucl. Energy, 87 (2016) 591-600.
Dorval, E. (2016c) "A comparative study of leakage and diffusion coefficient models for few-group cross section generation with the Monte Carlo method." Ann. Nucl. Energy, 90 (2016) 353-363.
Dorval, E. (2016d) "Monte Carlo methodologies for neutron streaming in diffusion calculations - Application to directional diffusion coefficients and leakage models in XS generation." D.Sc. Thesis, Aalto University, 2016.
Dufek, J. and Valtavirta, V. (2014) "Time step length versus efficiency of Monte Carlo burnup calculations." Ann. Nucl. Energy, 72 (2014) 409-412.
Fridman, E. and Leppänen, J. (2011) "On the use of the Serpent Monte Carlo code for few-group cross section generation." Ann. Nucl. Energy, 38 (2011) 1399-1405.
Fridman, E. and Leppänen, J. (2012a) "Revised methods for few-group cross section generation in the Serpent Monte Carlo code." In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
Ikonen, T. (2013a) "FINIX - fuel behavior model and interface for multiphysics applications - code documentation for version 0.13.9." VTT-R-06563-13, VTT Technical Research Centre of Finland, 2013.
Ikonen, T., Tulkki, V., Syrjälahti, E., Valtavirta, V. and Leppänen, J. (2013b) "FINIX - fuel behavior model and interface for multiphysics applications." In proc. TopFuel 2013, Charlotte, NC, Sept. 15-19, 2013.
Ikonen, T., Loukusa, H., Syrjälahti, E., Valtavirta, V., Leppänen, J. and Tulkki, V. (2015) "Module for thermomechanical modeling of LWR fuel in multiphysics simulations." Ann. Nucl. Energy, 84 (2015) 111-121.
Ikonen, T., Syrjälahti, E., Valtavirta, V., Loukusa, H., Leppänen, J. and Tulkki, V. (2016) "Multiphysics simulation of fast transients with the FINIX fuel behaviour module." EPJ Nuclear Sci. Technol., 2 (2016) Article 37.
Isotalo, A. (2009) "Improved TTA methods for the reactor physics code Serpent." Special assignment, Helsinki University of Technology, 2009.
Isotalo, A. (2010) "Improved time integration methods for burnup calculations with full systems of nuclides." M.Sc. Thesis, Helsinki University of Technology, 2010.
Isotalo, A. and Aarnio, P. (2011a) "Comparison of depletion algorithms for large systems of nuclides." Ann. Nucl. Energy, 38 (2011) 261-268.
Isotalo, A. and Aarnio, P. (2011b) "Higher order methods for burnup calculations with Bateman solutions." Ann. Nucl. Energy, 38 (2011) 1987-1995.
Isotalo, A. and Aarnio, P. (2011c) "Substep methods for burnup calculations with Bateman solution." Ann. Nucl. Energy, 38 (2011) 2509-2514.
Isotalo, A., Leppänen, J. and Dufek, J. (2013a) "Preventing xenon oscillations in Monte Carlo burnup calculations by enforcing equilibrium distribution." Ann. Nucl. Energy, 60 (2013) 78-85.
Isotalo, A. (2013b) "Computational methods for burnup calculations with Monte Carlo neutronics." D.Sc. Thesis, Aalto University, 2013.
Isotalo, A. and Sahlberg, V. (2015a) "Comparison of Neutronics-Depletion Coupling Schemes for Burnup Calculations." Nucl. Sci. Eng., 179 (2015) 434-459.
Isotalo, A. (2015b) "Comparison of Neutronics-Depletion Coupling Schemes for Burnup Calculations -- Continued Study." Nucl. Sci. Eng., 180 (2015) 286-300.
Kaltiaisenaho, T. (2014a) "Statistical tests and the underestimation of variance in Serpent 2." VTT-R-00371-14, VTT Technical Research Centre of Finland, 2014.
Kaltiaisenaho, T. and Leppänen, J. (2014b) "Analysing the Statistics of Group Constants Generated by Serpent 2 Monte Carlo Code." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Kaltiaisenaho, T. (2016) "Implementing a photon physics model in Serpent 2." M.Sc. Thesis, Aalto University, 2016.
Leppänen, J. (2005a) "Diffusion code group constant generation using the Monte Carlo method." In proc. XII Meeting on Reactor Physics in the Nordic Countries, Halden, Norway, 17-18 May, 2005.
Leppänen, J. (2005b) "A new assembly-level Monte Carlo neutron transport code for reactor physics calculations." In proc. M&C 2005, Avignon, France, Sept. 12-15, 2005.
Leppänen, J. (2006) "Current status of the PSG Monte Carlo neutron transport code." In proc. PHYSOR 2006, Vancouver, BC, Canada, Sept. 10-14, 2006.
Leppänen, J. (2007a) "VVER-440 local power peaking experiment benchmark." VTT-R-02688-07, VTT Technical Research Centre of Finland, 2007.
Leppänen, J. (2007b) "Randomly dispersed particle fuel model in the PSG Monte Carlo neutron transport code." In proc. M&C + SNA 2007 Monterey, CA, Apr. 15-18, 2007
Leppänen, J. (2007c) "Development of a new Monte Carlo reactor physics code." D.Sc. Thesis, Helsinki University of Technology, 2007. (VTT Publications 640)
Leppänen, J. (2008a) "PSG status report (March 2008)." VTT-R-02580-08, VTT Technical Research Centre of Finland, 2008.
Leppänen, J. (2008b) "On the feasibility of a homogenised multi-group Monte Carlo method in reactor analysis." In proc. PHYSOR 2008, Interlaken, Switzerland, Sept. 14-19, 2008.
Leppänen, J. and Pusa, M. (2009a) "Burnup calculation capability in the PSG2 / Serpent Monte Carlo reactor physics code." In proc. M&C 2009, Saratoga Springs, NY, May 3-7, 2009.
Leppänen, J. (2009b) "Two practical methods for unionized energy grid construction in continuous-energy Monte Carlo neutron transport calculation." Ann. Nucl. Energy, 36 (2009) 878-885.
Leppänen, J. (2009c) "On the use of the continuous-energy Monte Carlo method for lattice physics applications." In proc. INAC 2009, Rio de Janeiro, Brazil, Sept. 27 - Oct. 2, 2009.
Leppänen, J., DeHart, M. (2009d) "HTGR reactor physics and burnup calculations using the Serpent Monte Carlo code." Trans. Am. Nucl. Soc., 101 (2009) 782-784.
Leppänen, J. (2010a) "Serpent progress report 2009." VTT-R-01296-10, VTT Technical Research Centre of Finland, 2010.
Leppänen, J. (2010b) "Performance of Woodcock delta-tracking in lattice physics applications using the Serpent Monte Carlo reactor physics burnup calculation code." Ann. Nucl. Energy, 37 (2010) 715-722.
Leppänen, J. (2010c) "HTGR modeling capabilities in the Serpent Monte Carlo code." In proc. IYNC-2010, Cape Town, South Africa, Jul. 12-18, 2010.
Leppänen, J. (2010d) "Serpent Monte Carlo Reactor Physics Code." In proc. 20th AER Symposium on VVER Reactor Physics and reactor safety, Espoo, Finland, Sept. 20-24, 2010.
Leppänen, J. (2010e) "Use of the Serpent Monte Carlo reactor physics code for full-core calculations." In proc. SNA + MC 2010, Tokyo, Japan, Oct. 17-21, 2010.
Leppänen, J. (2011) "Serpent progress report 2010." VTT-R-01362-11, VTT Technical Research Centre of Finland, 2010.
Leppänen, J. and Isotalo, A. (2012a) "Burnup calculation methodology in the Serpent 2 Monte Carlo code." In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
Leppänen, J. (2012b) "Serpent progress report 2011." VTT-R-05444-12, VTT Technical Research Centre of Finland, 2012.
Leppänen, J., Viitanen, T. and Valtavirta, V. (2012c) "Multi-physics coupling scheme in the Serpent 2 Monte Carlo code." Trans. Am. Nucl. Soc., 107 (2012) 1165-1168.
Leppänen, J. (2013a) "Development of a dynamic simulation mode in the Serpent 2 Monte Carlo code." In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
Leppänen, J. (2013b) "Modeling of nonuniform density distributions in the Serpent 2 Monte Carlo code." Nucl. Sci. Eng., 174 (2013) 318-325.
Leppänen, J. (2014a) "Serpent progress report 2012." VTT-R-00300-14, VTT Technical Research Centre of Finland, 2014.
Leppänen, J., Aufiero, M., Fridman, E., Rachamin, R. and van der Marck, S. (2014b) "Calculation of effective point kinetics parameters in the Serpent 2 Monte Carlo code." Ann. Nucl. Energy, 65 (2014) 272-279.
Leppänen, J., Mattila, R. and Pusa, M. (2014c) "Validation of the Serpent-ARES code sequence using the MIT BEAVRS benchmark - Initial core at HZP conditions." Ann. Nucl. Energy, 69 (2014) 212-225.
Leppänen, J. and Aufiero, M. (2014d) "Development of an Unstructured Mesh Based Geometry Model in the Serpent 2 Monte Carlo Code." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Leppänen, J., Valtavirta, V., Viitanen, T. and Aufiero, M. (2014e) "Unstructured Mesh Based Multi-Physics Interface for CFD Code Coupling in the Serpent 2 Monte Carlo Code." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Leppänen, J. (2014f) "Development of a CAD Based Geometry Model in Serpent 2 Monte Carlo Code." Trans. Am. Nucl. Soc., 111 (2014) 663-667.
Leppänen, J. (2015a) "CAD-based Geometry Type in Serpent 2 -- Application in Fusion Neutronics." In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
Leppänen, J., Pusa, M., Viitanen, T., Valtavirta, V. and Kaltiaisenaho, T. (2015b) "The Serpent Monte Carlo code: Status, development and applications in 2013." Ann. Nucl. Energy, 82 (2015) 142-150.
Leppänen, J., Hovi, V., Ikonen, T., Kurki, J., Pusa, M., Valtavirta, V. and Viitanen, T. (2015c) "The Numerical Multi-Physics project (NUMPS) at VTT Technical Research Centre of Finland." Ann. Nucl. Energy, 84 (2015) 55-62.
Leppänen, J. and Mattila, R. (2015d) "Study on computational performance in generation of cross sections for nodal simulators using continuous-energy Monte Carlo calculations." J. Nucl. Sci. Technol., 52 (2015) 945-952.
Leppänen, J. and Kaltiaisenaho, T. (2016a) "Expanding the Use of Serpent 2 to Fusion Applications: Shut-down Dose Rate Calculations." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Leppänen, J., Pusa, M. and Fridman, E. (2016b) "Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code." Ann. Nucl. Energy, 96 (2016) 126-136.
Leppänen, J. and Mattila, R. (2016c) "Validation of the Serpent-ARES code sequence using the MIT BEAVRS benchmark – HFP conditions and fuel cycle 1 simulations." Ann. Nucl. Energy, 96 (2016) 324-331.
Pusa, M. and Leppänen, J. (2010) "Computing the matrix exponential in burnup calculations." Nucl. Sci. Eng., 164 (2010) 140-150.
Pusa, M. (2011) "Rational approximations to the matrix exponential in burnup calculations." Nucl. Sci. Eng., 169 (2011) 155-167.
Pusa, M. and Leppänen, J. (2012) "An efficient implementation of the Chebyshev rational approximation method (CRAM) for solving the burnup equations." In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
Pusa, M. (2013a) "Accuracy considerations for Chebyshev rational approximation method (CRAM) in burnup calculations." In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
Pusa, M. (2013b) "Numerical methods for nuclear fuel burnup calculations." D.Sc. Thesis, Aalto University, 2013. (VTT Science 32)
Pusa, M. and Leppänen, J. (2013c) "Solving linear systems with sparse Gaussian elimination in the Chebyshev rational approximation method (CRAM)." Nucl. Sci. Eng., 175 (2013) 250-258.
Pusa, M. (2013d) "Correction to partial fraction decomposition coefficients for Chebyshev rational approximation on the negative real axis." arXiv:1206.2880v1 [math.NA].
Pusa, M. (2014) "Higher-Order Chebyshev Rational Approximation Method (CRAM)." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Sirén, P. and Leppänen, J. (2016) "Expanding the use of Serpent 2 to Fusion Applications: Development of a Plasma Neutron Source." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Valtavirta, V. (2012) "Designing and implementing a temperature solver routine for Serpent." M.Sc. Thesis, Aalto University, 2012.
Valtavirta, V. (2013a) "Internal Neutronics-temperature coupling in Serpent 2 -- Reactivity differences resulting from choice of material property correlations." In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
Valtavirta, V., Tulkki, V., Leppänen, J. and Viitanen, T. (2013b) "The universal fuel performance code interface in Serpent 2." In proc. TopFuel 2013, Charlotte, NC, Sept. 15-19, 2013.
Valtavirta, V., Viitanen, T. and Leppänen, J. (2014a) "Internal neutronics-temperature coupling in Serpent 2." Nucl. Sci. Eng., 177 (2014) 193-202.
Valtavirta, V., Ikonen, T., Viitanen, T. and Leppänen, J. (2014b) "Simulating Fast Transients with Fuel Behavior Feedback Using the Serpent 2 Monte Carlo Code." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Valtavirta, V. (2015) "Uncertainty Underprediction in Coupled Time-Dependent Monte Carlo Simulations with Serpent 2." In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
Valtavirta, V., Hessan, M. and Leppänen, J. (2016) "Delayed Neutron Emission Model for Time Dependent Simulations with the Serpent 2 Monte Carlo Code - First Results." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Valtavirta, V., Leppänen, J. and Viitanen, T. (2017) "Coupled neutronics–fuel behavior calculations in steady state using the Serpent 2 Monte Carlo code." Ann. Nucl. Energy, 100 (2017) 50-64.
Viitanen, T. (2009) "Implementing a Doppler-preprocessor of cross section libraries in reactor physics code Serpent." M.Sc. Thesis, Helsinki University of Technology, 2009.
Viitanen, T. and Leppänen, J. (2011a) "New Data processing features in the Serpent Monte Carlo code." J. Korean Phys. Soc 59 (2011) 1365-1368.
Viitanen, T. (2011b) "Serpent-ENIGMA - Combining Monte Carlo reactor physics with fuel performance." VTT-R-06265-11, VTT Technical Research Centre of Finland, 2011.
Viitanen, T. and Leppänen, J. (2012a) "Explicit treatment of thermal motion in continuous-energy Monte Carlo tracking routines." Nucl. Sci. Eng., 171 (2012) 165-173.
Viitanen, T. and Leppänen, J. (2012b) "Explicit temperature treatment in Monte Carlo neutron tracking routines -- First results." In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
Viitanen, T and Tulkki, V. (2012c) "Combining reactor physics and fuel performance calculations." In proc. TopFuel 2012, Manchester, UK, Sept. 2-6, 2012.
Viitanen, T. and Leppänen, J. (2012d) "Intelligent nuclide selection capability in the reactor physics and inventory calculation code Serpent 2." In proc. 12IEMPT, Prague, Czech Republic, Sept. 24-27, 2012.
Viitanen, T. and Leppänen, J. (2013a) "Optimizing the implementation of the target motion sampling temperature treatment technique -- How fast can it get?" In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
Viitanen, T. and Leppänen, J. (2014a) "Target motion sampling temperature treatment technique with elevated basis cross section temperatures." Nucl. Sci. Eng., 177 (2014) 77-89.
Viitanen, T. and Leppänen, J. (2014b) "Validating the Serpent Model of FiR 1 Triga Mk-II Reactor by Means of Reactor Dosimetry." In proc. 15th ISRD, Aix en Provence, France, May. 18-23, 2014.
Viitanen, T., Leppänen, J. and Forget, B. (2014c) "Target Motion Sampling Temperature Treatment Technique with Track-Length Estimators in OpenMC -- Preliminary Results." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Viitanen, T. (2015a) "Development of a stochastic temperature treatment technique for Monte Carlo neutron tracking." D.Sc. Thesis, Aalto University, 2015. (VTT Science 84)
Viitanen, T. and Leppänen, J. (2015b) "Effect of the target motion sampling temperature treatment method on the statistics and performance." Ann. Nucl. Energy, 82 (2015) 217-225.
Viitanen, T. and Leppänen, J. (2015c) "Temperature Majorant Cross Sections in Monte Carlo Neutron Tracking." Nucl. Sci. Eng., 180 (2015) 209-223.
Viitanen, T. and Leppänen, J. (2016) "New Interpolation Capabilities for Thermal Scattering Data in Serpent 2." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.

Theses and student projects with Serpent applications

Alameri, S. (2015) "A coupled nuclear reactor thermal energy storage system for enhanced load following operation." Ph.D. Thesis, Colorado School of Mines, 2015.
Alhassan, E. (2015a) "Nuclear data uncertainty quantification and data assimilation for a lead -cooled fast reactor: Using integral experiments for improved accuracy." Ph.D. Thesis, Uppsala University, 2015.
Andrews, N. (2015) "Application of advanced fuel concepts for use in innovative pressurized water reactors." Ph.D. Thesis, Massachusetts Institute of Technology, 2015.
Aufiero, M. (2014b) "Development of advanced simulation tools for circulating fuel nuclear reactors." Ph.D. Thesis, Politecnico di Milano, 2014.
Aures, A. (2012) "Nuklidinventarbestimmung eines gesamten Leichtwasserreaktorkerns vom Typ Konvoi im Gleichgewichtszustand unter Anwendung des Reaktorphysik-Programms Serpent." Diploma Thesis, RWTH Aachen University, 2012 (in German).
Baldova, D. (2014) "Feasibility study on high-conversion Th-U233 fuel cycle for current generation of PWRs." Ph.D. Thesis, Technical University of Prague, 2014.
Barray, C. (2012) "Monte Carlo simulation of a nuclear research reactor type TRIGA with Serpent code." Internship Report, Aalto University, 2012.
Bean, M. (2011) "Computational neutronics analysis of TRIGA reactors during power pulsing." B.Sc. Thesis, Massachusetts Institute of Technology, 2011.
Bergmann, R. (2015) "The Development of WARP - A Framework for Continuous Energy Monte Carlo Neutron Transport in General 3D Geometries on GPUs." Ph.D. Thesis, University of California, Berkeley, 2015.
Cai, L. (2015) "Condensation and homogenization of cross sections for the deterministic transport codes with Monte Carlo method : Application to the GEN IV fast neutron reactors." Ph.D. Thesis, Université Grenoble Alpes, 2015.
Castagna, C. (2014) "Modellizzazione al simulatore delle condizioni di criticitŕ del reattore TRIGA Mark II a diversi livelli di potenza." M.Sc. Thesis, University of Milano-Bicocca, 2014 (in Italian).
Changizi, S. (2012) "Neutronic Analysis of the Multipurpose Hybrid Research Reactor for High-tech Applications (MYRRHA) with a Monte Carlo Code SERPENT." M.Sc. Thesis, Royal Institute of Technology, 2012.
Chersola, D. (2016) "Application of new neutronic and burnup Monte Carlo based codes to the study of nuclear fuel cycles for GFR and VVER systems." Ph.D. Thesis, University of Genova, 2016.
Descotes, M. (2011) "Reactor Physics of a Deep-burner Prismatic Core for VHTR." M.Sc. Thesis, École Polytechnique de Montréal, 2016.
De Lorenzo, M. (2015) "Implementation of a Full 3D Neutronic Model for Myrrha in RELAP5-3D using Nestle." M.Sc. Thesis, Politecnico di Torino, 2015.
DeWitte, J. (2014) "Maximizing nuclear power plant performance via mega-uprates and subsequent license renewal." Ph.D. Thesis, Massachusetts Institute of Technology, 2014.
Díez Fernández, G. (2012) "Safety aspects of Ceramic Fully Encapsulated fuel for Light Water Reactors." M.Sc. Thesis, Universitat Politčcnica de Catalunya (UPC) / Royal Institute of Technology, 2012.
Duerigen, S. (2013) "Neutron Transport in Hexagonal Reactor Cores Modeled by Trigonal-Geometry Diffusion and Simplified P3 Nodal Methods." Ph.D. Thesis, Karlsruhe Institute of Technology, 2013.
Elgin, K. (2014) "A study of the feasibility of 99Mo production inside the TU Delft Hoger Onderwijs Reactor." B.Sc. Thesis, Technical University of Deflt, 2014.
Eloranta, K (2013) "RBMK-koereaktorin mallintaminen." B.Sc. Thesis, Lappeenranta University of Technology, 2013 (in Finnish).
Falaakh, D. (2016) "Neutronic Analysis of Reduced Moderation Boiling Water Reactor 1050 MWt." B.Sc. Thesis, Universitas Gadjah Mada, 2016.
Fernández Navarro, A. (2014) "Impact of fusion neutrons on helium production in beryllium and tungsten, and tritium breeding in ITER and DEMO." M.Sc. Thesis, Aalto University, 2014.
Fredriksson, P. (2014) "Determination of Radial Power Profiles in Thorium-Plutonium Mixed Oxide Fuel Pellets." M.Sc. Thesis, Chalmers University of Technology, 2014.
Garcia, R. (2012) "A Paranetric Study on Core Performance of Sodium Fast Reactors Using SERPENT Code." M.Sc. Thesis, Royal Institute of Technology, 2012.
Garcia Domínguez, C. (2013) "Generation of nuclear data for Lead-cooled Fast Reactor using the Monte Carlo method." M.Sc. Thesis, Politecnico di Torino, Torino, 2013.
Gentry, C. (2016) "Development of a Reactor Physics Analysis Procedure for the Plank-Based and Liquid Salt-Cooled Advanced High Temperature Reactor." Ph.D. Thesis, University of Tennessee, 2012.
Ghasabyan, L. (2013) "Use of Serpent Monte Carlo code for development of 3D full-core models of Gen-IV fast-spectrum reactors and preparation of group constants for transient analyses with PARCS/TRACE coupled system." M.Sc. Thesis, Royal Institute of Technology, 2013.
Hall, A (2015) "Homogenization Methods for Full Core Solution of the Pn Transport Equations with 3-D Cross Sections." Ph.D. Thesis, University of Michigan, 2015.
Halla-Aho, L (2013) "Simulation of the Interaction Mean Free Path Between Neutrons and TRISO Particles." B.Sc. Thesis, Lappeenranta University of Technology, 2013.
Hanlon, B. (2015) "Validation of the use of low enriched uranium as a replacement for highly enriched uranium in US submarine reactors." M.Sc. Thesis, Massachusetts Institute of Technology, 2015.
Harris, A. (2013) "Heavy water as a thorium breeder reactor coolant." M.Sc. Thesis, University of Cambridge, 2013.
Hassan, S. (2011) "Spatial dependence of reactivity coefficients." M.Sc. Thesis, Royal Institute of Technology, 2011.
Herman, B. (2011) "Cross section generation strategy for high conversion light water reactors." M.Sc. Thesis, Massachusetts Institute of Technology, 2011.
Hermawan, D. (2016) "Analysis of Fuel Assembly Design in Small PWR using Uranium Nitride-Based Fully Ceramic Microencapsulated Fuel on Soluble Boron Free Operational Condition." B.Sc. Thesis, Universitas Gadjah Mada, 2016.
Hidayatullah, R. (2014) "A Novel Research Reactor Concept Based on Coated Particle Fuel." M.Sc. Thesis, Korea Advanced Institute of Science and Technology, 2014.
Hyvärinen, J-P. (2012) "HTR-PROTEUS-reaktorin mallintaminen." B.Sc. Thesis, Lappeenranta University of Technology, 2012 (in Finnish).
Hyvönen, O. (2015) "Finding optimal reconstruction parameters for cross section libraries used with Serpent 2." B.Sc. Thesis, Aalto University, 2015.
Inkinen, P. (2009) "Implementation of nodal diffusion model into APROS." M.Sc. Thesis, Helsinki University of Technology, 2009.
Johns, J. (2014) "Physics-based Predictive Time Propagation Method for Monte Carlo Coupled Depletion Simulations." Ph.D. Thesis, Texas A&M University, 2014.
Juutilainen, P. (2009) "Burnup credit benchmark calculation with Monte Carlo method." Special assignment, Helsinki University of Technology, 2009. (VTT-R-06819-09)
Kalinainen, T. (2016) "Modelling of Decay Heat with Exponential Functions in Serpent 2." Special assignment, Aalto University, 2016.
Karriem, V. (2016) "The Development of a Thermal Hydraulic Feedback Mechanism with a Quasi-fixed Point Iteration Scheme for Control Rod Position Modeling for the TRIGSIMS-TH Application." Ph.D. Thesis, Pennsylvania State University, 2016.
Kelm, C. (2012) "Auswirkung einer Langzeitzwischenlagerung auf abgebrannten DWR Kernbrennstoff und Szenarien zur zukünftigen Wiederverwendung." Diploma Thesis, RWTH Aachen University, 2012 (in German).
Kim, H. (2015) "Static and transient analysis of Molten Salt Reactor Experiment using SERPENT-2/TRACE/PARCS code." M.Sc. Thesis, École Polytechnique Fédérale de Lausanne / Eidgenössische Technische Hochschule Zürich, 2015.
Kim, W. (2013a) "Improvement of CANDU safety parameters by using CANFLEX." M.Sc. Thesis, Korea Advanced Institute of Science and Technology, 2013.
Kim, Y. (2012) "Preliminary Analysis of Neutronic Parameters of European Lead Cooled Training Reactor (ELECTRA)." M.Sc. Thesis, École Polytechnique Fédérale de Lausanne / Eidgenössische Technische Hochschule Zürich, 2012.
Kotlyar, D. (2013) "Development of Advanced Burnup-Thermal Hydraulic Coupling Methods for Monte Carlo Codes." Ph.D. Thesis, Ben-Gurion University of the Negev, 2013.
Kuopanportti, J. (2009) "Radkowsky-nipun suorituskyky ja vaikutus neutroniikkaan tyypillisessä painevesireaktorissa." B.Sc. Thesis, Helsinki University of Technology, 2009 (in Finnish).
Kuopanportti, J. (2010) "CASMO-4E simulations of the Radkowsky Thorium Fuel concept." Special assignment, Aalto University, 2010.
Kähärä, R. (2015) "Simulating gamma transport with Serpent." B.Sc. Thesis, Aalto University, 2015.
Laaksoviita, T. (2013) "Simplified modelling of a fresh pressurized water reactor core by diffusion theory." B.Sc. Thesis, Aalto University, 2013.
Laureau, A. (2015) "Développement de modčles neutroniques pour le couplage thermohydraulique du MSFR et le calcul de paramčtres cinétiques effectifs." Ph.D. Thesis, Université Grenoble Alpes, 2015 (in French).
Laurier, A. (2016) "Implementation of the SPH procedure within the Moose finite element framework." M.Sc. Thesis, École Polytechnique de Montréal, 2016.
Lázaro, A. (2014) "Development, Assessment and Application of Computational Tools for Design Safety Analysis of Liquid Metal Cooled Fast Breeder Reactors." Ph.D. Thesis, University of Valencia, 2014.
Lu, Q. (2014) "Stability analysis of a natural circulation lead-cooled fast reactor." M.Sc. Thesis, University of Illinois, 2014.
Luszczek, K. (2015) "Validation and Benchmarking of Westinghouse Lattice Physics Methods." M.Sc. Thesis, Royal Institute of Technology, 2015.
Lyons, J. (2013) "Reactor physics model of the advanced test reactor using TRIGA fuel through application of Serpent 2." M.Sc. Thesis, Oregon State University, 2013.
Lyu, J. (2016) "(An) innovative way of Co-60 production in CANDU6 reactors." M.Sc. Thesis, Korea Advanced Institute of Science and Technology, 2016.
Mahjoub, M. (2016) "Développement d'une méthode de Monte Carlo dépendante dutemps et application au réacteur de type CANDU-6." Ph.Dc. Thesis, École Polytechnique de Montréal, 2016 (in French).
Martin, N. (2011) "Application de la méthode des sous-groupes au calcul Monte-Carlo multigroupe." Ph.D. Thesis, École Polytechnique de Montréal, 2011 (in French).
Macdonald, R. (2014) "Investigation and design of a secure, transportable fluoride-salt-cooled high-temperature reactor (TFHR) for isolated locations." M.Sc. Thesis, Massachusetts Institute of Technology, 2014.
Metsälä, M. (2016) "Accurate Heat Deposition Calculations in Nuclear Reactors Using Monte Carlo Neutron and Photon Transport." Special assignment, Aalto University, 2016.
Mettälä, J. (2012) "Vaikutusalakirjastojen muodostaminen Serpent-ARES-laskentaketjussa." M.Sc. Thesis, Lappeenranta University of Technology, 2012 (in Finnish).
Mieloszyk, A. (2015) "Assessing thermo-mechanical performance of ThO2 and SiC clad light water reactor fuel rods with a modular simulation tool." Ph.D. Thesis, Massachusetts Institute of Technology, 2015.
Ochoa, R. (2014) "Core physics and safety analysis of Generation-IV Sodium Fast Reactors using existing and newly developed computational tools." Ph.D. Thesis, Universidad Politécnica de Madrid, 2014.
Panadero, A. (2014) Static neutronic, thermal-hydraulic, and fuel performance analysis of the ASTRID Sodium-cooled Fast Reactor core." M.Sc. Thesis, École Polytechnique Fédérale de Lausanne / Eidgenössische Technische Hochschule Zürich, 2014.
Patel, V. (2012) "A Multi-Modular Neutronically Coupled Power Generation System." M.Sc. Thesis, Texas A&M University, 2012.
Pettersen, E. (2016) Coupled multi-physics simulations of the Molten Salt Fast Reactor using coarse-mesh thermal-hydraulics and spatial neutronics." M.Sc. Thesis, Université Paris-Saclay, 2016.
Preciado, M. (2014) "Development of a KONVOI PWR Core Model for Coupled TRACE/PARCS Simulations." B.Sc. Thesis, Universitat Polytecnica de Valencia, 2014.
Qvist, S. (2013) "Core design and safety of large liquid metal cooled fast breeder reactors." Ph.D. Thesis, University of California Berkeley, 2013.
Raub, S. (2011) "Transient behaviour in a BWR with Hafnium Cladding." M.Sc. Thesis, Royal Institute of Technology, 2011.
Richard, J. (2016) "Design optimization and analysis of a fluoride salt cooled high temperature test reactor for accelerated fuels and materials testing and nonproliferation and safeguards evaluations." Ph.D. Thesis, Massachusetts Institute of Technology, 2016.
Rintala, A. (2012) "Effect of temperature discretization on the results of neutronics calculations." B.Sc. Thesis, Aalto University, 2012.
Rintala, A. (2013) "Error of multigroup energy discretization in fast reactors." Special assignment, Aalto University, 2012.
Rintala, A. (2015) "Development and validation of Apros multigroup nodal diffusion model." M.Sc. Thesis, Aalto University, 2015.
Rintala, V. (2011) "Monte Carlo -reaktorifysiikkalaskennan ja laskennallisen virtausmekaniikan kytkentä kuulakekoreaktorissa." M.Sc. Thesis, Lappeenranta University of Technology, 2011 (in Finnish).
Sahlberg, V. (2013) "Comparison of coupling schemes for Monte Carlo burnup calculations." B.Sc. Thesis, Aalto University, 2013.
Sahlberg, V. (2014) "Development of Serpent 2 – TRAB3D code sequence." Special assignment, Aalto University, 2014. (VTT-R-04538-14)
Sahlberg, V. (2015) "Validating Pin Power Reconstruction Module with Serpent 2 – TRAB3D Code Sequence." Special assignment, Aalto University, 2015. (VTT-R-04065-15)
Sahlberg, V. (2016) "Modelling of axial discontinuities in reactor cores with Serpent 2 - TRAB3D code sequence." M.Sc. Thesis, Aalto University, 2016.
Samaropoulos, I. (2013) "Development of SERPENT based equilibrium fuel cycle procedure EQL0D." M.Sc. Thesis, École Polytechnique Fédérale de Lausanne / Eidgenössische Technische Hochschule Zürich, 2013.
Shapiro, R. (2014) "Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel." M.Sc. Thesis, Pennsylvania State University, 2014.
Shirvan, K. (2013) "Development of optimized core design and analysis methods for high power density BWRs." Ph.D. Thesis, Massachusetts Institute of Technology, 2013.
Scherr, J. (2016) "Fast Spectrum Material’s Testing Reactor with Variable Energy Spectra to Support Advanced Reactors Program and Light Water Reactor Sustainability Program R&D." M.Sc. Thesis, Texas A&M University, 2016.
Schäfer, K. (2013a) "Simulation des Erstkritikalitätsexperimentes des THTR-300 unter Anwendung des Reaktorphysik-Programms Serpent." Minor Thesis, RWTH Aachen University, 2013 (in German).
Schäfer, K. (2013b) "Simulation kritischer Benchmarkexperimente mit einfacher Geometrie unter Anwendung des Reaktorphysik-Programms Serpent." Minor Thesis, RWTH Aachen University, 2013 (in German).
Schäfer, K. (2014) "Untersuchungen zur Qualität der Graphit-Wirkungsquerschnitte anhand von Benchmarkexperimenten." Diploma Thesis, RWTH Aachen University, 2014 (in German).
Scriven, M. (2015) "Senstivity of Lattice Physics Modelling of the Canadian PT-SCWR to Changes in Lateral Coolant Density Gradients in a Channel." M.Sc. Thesis, McMaster University, 2015.
Seppälä, M. (2008) "Neutronic and Thermal-hydraulic Modelling of High Performance Light Water Reactor." M.Sc. Thesis, Helsinki University of Technology, 2008.
Suvdantsetseg, E. (2014b) "Neutronics and Transient Analysis of a Small Fast Reactor Cooled with Natural Circulation of Lead: ELECTRA: European Lead Cooled Training Reactor." Ph.D. Thesis, Royal Institute of Technology, 2014.
Taavitsainen, A. (2016) "CFENSS-SRS method for the uncertainty analysis of nuclear fuel and neutronics." M.Sc. Thesis, Aalto University, 2016.
Tantillo, F. (2013) "Two dimensional extension of the integral neutronic transport code TOTMOS." Laurea Magistrale Ingegneria Energetica e Nucleare, Universita di Palermo, 2013.
Templeton, J. (2015) "SERPENT Modeling of the Transient Reactor Test Facility and Comparison with Measured Experimental Data." M.Sc. Thesis, University of New Mexico, 2015.
Tuominen, R. (2015) "Coupling Serpent and OpenFOAM for neutronics – CFD multi-physics calculations." M.Sc. Thesis, Aalto University, 2015.
Wolniewicz, P. (2012) "A feasibility study of coolant void detection in a lead-cooled fast reactor using fission chambers." Lic.Sc. Thesis, Uppsala University, 2012.
Wolniewicz, P. (2014) "Development of a Methodology for Detecting Coolant Void in Lead-cooled Fast Reactors by Means of Neutron Measurements." D.Sc. Thesis, Uppsala University, 2014.
Wyant, T. (2012a) "Numerical study of error propagation in Monte Carlo depletion simulations." M.Sc. Thesis, Georgia Institute of Technology, 2012.
Wu, X. (2013) "Coupling of system thermal-hydraulics and Monte-Carlo method for a consistent thermal-hydraulics-reactor physics feedback." M.Sc. Thesis, University of Illinois, 2013.
Younker, I. (2015) "Neutronic and Economic Evaluation of Accident Tolerant Fuel Concepts for Light Water Reactors." M.Sc. Thesis, Pennsylvania State University, 2015.
Yu, H. (2014) "Low-boron OPR1000 core based on the BigT burnable absorber." M.Sc. Thesis, Korea Advanced Institute of Science and Technology, 2014.
Zhang, Y. (2011) "Transmutation of Americium in Fast Neutron Facilities." Lic.Sc. Thesis, Royal Institute of Technology, 2011.
Zhang, Y. (2012) "Transmutation of Am in sodium fast reactors and accelerator driven systems." D.Sc. Thesis, Royal Institute of Technology, 2012.
Zilly, A. (2014) "Modellierung und Simulation der HTR-Experimente am Siemens Argonaut-Reaktor in Graz." Minor Thesis, RWTH Aachen University, 2014 (in German).

Publications and reports related to Serpent applications

Agung, A. (2016) "Neutronic assessment on the use of advanced coated particles in a fluidized bed nuclear reactor." J. Eng. Appl. Sci., 11 (2016) 7059-7067.
Alberti A., Palmer, T., Ortensi J. and DeHart, M. (2016) "Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Alcaro, F, Dulla, S. and Ravetto P. (2013) "Neutronic Evaluations for the EVOL Molten Salt Reactor." Trans. Am. Nucl. Soc., 108 (2013) 927-930.
Alferov, V., Radaev, A., Shchurovskaya, A., Tikhomirov, G., Hanan, N. and van Heerden, F. (2015) "Comparative validation of Monte Carlo codes for the conversion of a research reactor." Ann. Nucl. Energy, 77 (2015) 273-280.
Alhassan, E., Sjöstrand, H., Duan, J., Gustafsson, C., Pomp, S., Österlund, M., Rochman, D. and Koning, A. (2013) "Uncertainty of lead cross sections on reactor safety for ELECTRA." In proc. SNA + MC 2013, Paris, France, Oct. 27-31, 2013.
Alhassan, E., Sjöstrand, H., Duan, J., Gustavsson, C., Koning, A., Pomp, S., Rochman, D. and Österlund, M. (2014a) "Combining Total Monte Carlo and Benchmarks for Nuclear Data Uncertainty Propagation on a Lead Fast Reactor's Safety Parameters." Nucl. Data Sheets, 118 (2014) 542-544.
Alhassan, E., Sjöstrand, H., Duan, J., Helgesson, P., Pomp, S., Österlund, M., Rochman, D. and Koning, A. (2014b) "Selecting Benchmarks for Reactor Calculations." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Alhassan, E., Sjöstrand, H., Helgesson, P., Koning, A., Österlund, M., Pomp, S. and Rochman, D. (2015b) "Uncertainty and correlation analysis of lead nuclear data on reactor parameters for the European Lead Cooled Training Reactor." Ann. Nucl. Energy, 75 (2015) 26-37.
Alhassan, E., Sjöstrand, H., Helgesson, P., Österlund, M., Pomp, S., Koning, A. and Rochman, D. (2016) "Selecting benchmarks for reactor simulations: An application to a lead fast reactor." Ann. Nucl. Energy, 96 (2016) 158-169.
Alhassan, E., Sjöstrand, H., Helgesson, P., Österlund, M., Pomp, S., Koning, A. and Rochman, D. (2016) "On the use of integral experiments for uncertainty reduction of reactor macroscopic parameters within the TMC methodology." Prog. Nucl. Energy, 88 (2016) 43-52.
Allelein, H., Kasselmann, S., Xhonneux, A., Tantillo, F., Trabadela, A. and Lambertz, D. (2016a) "First results for fluid dynamics, neutronics and fission product behavior in HTR applying the HTR code package (HCP) prototype." Nucl. Eng. Design, 306 (2016) 145-153.
Allelein, H. and Verfondern, K. (2016b) "German HTR Phase Out - Experience and Remaining Challenges." In proc. HTR 2016, Las Vegas, NV, Nov. 6-10, 2016.
Andrews N., Shirvan K. and Kazimi M. (2013) "Viability of uranium nitride fueled high-conversion PWR." Prog. Nucl. Energy, 82 (2015) 28-32.
Antolin, M., Marinho, F., Palma, D. and Martinez, A. "Spallation Source Modelling for an ADS Using the MCNPX and GEANT4 Packages for Sensitivity Analysis of Reactivity." Nucl. Data Sheets, 118 (2014) 510-512.
Antolin, M., Martinez, A., Silva Fernando, F. and Palma, D. (2013) "Calculation of reactivity in subcritical reactors using the method of partial derivatives." Ann. Nucl. Energy, 60 (2013) 34-38.
Aufiero, M., Cammi, A., Fiorina, C., Luzzi, L. and Sartori, A. (2013b) "A multi-physics time-dependent model for the lead fast reactor single-channel analysis." Nucl. Eng. Design, 256 (2013) 14-27.
Aufiero, M., Cammi, A., Geoffroy, O., Losa, M., Luzzi, L., Ricotti, M. and Rouch, H. (2014a) "Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysis." Chem. Eng. Sci. 111(2014)390–401.
Aufiero, M., Fiorina, C., Laureau, A., Rubiolo, P. and Valtavirta, V. (2015) "Serpent-OpenFOAM Coupling in Transient Mode: Simulation of a Godiva Prompt Critical Burst." In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
Aufiero, M. and Fratoni, M. (2016a) "Development of Multiphysics Tools for Fluoride-cooled High-temperature Reactors." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Aufiero, M., Martin, M., Fratoni, M., Fridman, E. and Lorenzi, S. (2016b) "Analysis of the Coolant Density Reactivity Coefficient in LFRs and SFRs via Monte Carlo Perturbation/Sensitivity." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Aufiero, M., Martin, M. and Fratoni, M. (2016c) "Nuclear Data Uncertainty Quantification for Adjoint–Weighted Quantities via XGPT in Monte Carlo Codes." Trans. Am. Nucl. Soc., 113 (2016) 429-432.
Aures, A., Bostelmann, F., Hannstein, V., Velkov, K., Zwermann, W., Guilliard, N., Lapins, J. and Bernnat, W. (2015) "Depletion Calculation and Uncertainty / Sensitivity Analysis for a Sodium-cooled Fast Spectrum Fuel Assembly." In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
Baier, S., Fridman, E., Kliem, S. and Rohde, U. (2014) "Extension and application of the reactor dynamics code DYN3D for Block-type High Temperature Reactors." Nucl. Eng. Design, 271 (2014) 431-436.
Baldova, D. and Fridman, E. (2012) "High conversion Th-U233 fuel assembly for current generation of PWRs." In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
Baldova, D., Fridman, E. and Shwageraus, E. (2014) "High conversion Th-U233 fuel for current generation of PWRs: Part I – Assembly level analysis." Ann. Nucl. Energy, 73 (2014) 552-559.
Bilodid, Y., Fridman, E., Margulis, M., Kotlyar, D. and Shwageraus, E. (2014) "Verification of the Spectral History Correction Method with Fully Coupled Monte Carlo Code BGCore." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Bilodid, Y., Kotlyar, D., Margulis, M., Fridman, E. and Shwageraus. E. (2015) "Spectral history model in DYN3D: Verification against coupled Monte-Carlo thermal-hydraulic code BGCore." Ann. Nucl. Energy, 81 (2015) 34–40.
Bilodid, Y., Kotlyar, D., Shwageraus. E., Fridman, E. and Kliem, S. (2016) "Hybrid microscopic depletion model in nodal code DYN3D." Ann. Nucl. Energy, 92 (2016) 397-406.
Bilodid, Y., Fridman, E., Kliem, S., Kotlyar, D. and Shwageraus, E. (2016) "Microscopic Depletion with the Correction of Microscopic Cross Sections in Nodal Diffusion Code DYN3D." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Björk, K. and Fredriksson, P. (2014) "Development of a Fuel Performance Code for Thorium-Plutonium Fuel." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Bogetic, S., Greenop, A., Haneklaus, N., Poresky, C. and Shen D. (2016) "Near-Term Deployment Viability of Liquid-Fuel Molten Salt Reactors." Trans. Am. Nucl. Soc., 115 (2016) 73-76.
Boyarinov, V., Fomichenko P. and Grol, A. (2016) "Use of Cross-Section Covariance Information in Uncertainty Analysis at Modeling HTGR Neutron Physics." In proc. HTR 2016, Las Vegas, NV, Nov. 6-10, 2016.
Bortot, S., Wallenius, J., Suvdantsetseg, E. and Pelloni, S. (2013) "Modeling issues in small HLMC fast reactors: ELECTRA case study." Trans. Am. Nucl. Soc., 109 (2013) 2261-2264.
Bortot, S., Pelloni, S. and Mikityuk, K. (2014) "Methodology Assessnebt for the Evaluation of the Coolant Void Worth in Sodium Fast Reactors With a Low Void Effect Core Design." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Bostelmann, F., Hammer, H., Ortensi, J., Strydom, G., Velkov, K. and Zwermann, W. (2016) "Criticality calculations of the Very High Temperature Reactor Critical Assembly benchmark with Serpent and SCALE/KENO-VI." Ann. Nucl. Energy, 90 (2016) 343–352.
Bostelmann, F., Velkov K., Zwermann, W., Hammer, H. and Strydom G. (2016) "Impact of Nuclear Data Uncertainties on Criticality Calculations of the Very High Temperature Reactor Critical Assembly Benchmark." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Bostelmann, F., Strydom, G., Reitsma, F. and Ivanov, K. (2016) "The IAEA coordinated research programme on HTGR uncertainty analysis: Phase I status and Ex. I-1 prismatic reference results." Nucl. Eng. Design, 306 (2016) 77-88.
Bousquet, J., Seubert, A., Velkov, K. and Weiß, F. (2016) "Neutronic Modeling of the MYRRHA Minimum Critical Core with PARCS and Serpent." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Brankov, V., Khvostov, G., Mikityuk, K., Pautz, A., Restani, R., Abolhassani, S., Ledergerber, G. and Wiesenack, W. (2016) "Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high burnup KKL BWR fuels." Nucl. Eng. Design, 305 (2016) 559-568.
Brown, N., Ludewig, H., Aronson, A., Raitses, G. and Todosow, M. (2013a) "Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients." Ann. Nucl. Energy, 62 (2013) 538-547.
Brown, N., Ludewig, H., Aronson, A., Raitses, G. and Todosow, M. (2013b) "Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback." Ann. Nucl. Energy, 62 (2013) 548-557.
Brown, N., Aronson, A., Todosow, M., Brito, R. and McClellan, K. (2014a) "Neutronic performance of uranium nitride composite fuels in a PWR." Nucl. Eng. Design, 275 (2014) 393–407.
Brown, N., Aronson, A. and Todsow, M. (2014b) "BNL Metal Fuel Lattice Experiments: Candidates for Reactor Physics Benchmark Evaluation." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Brown, N., Raitses, G. and Todsow, M. (2014c) "Fuel Cycle Analysis of Self-Sustaining Water Cooled Reactors with 232Th/233U Fuel and Impact of 233U (n,g) Cross Section Evaluations." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Brown, N., Todsow, M. and McClellan, K. (2014d) "Uranium nitride composite fuels in a pressurized water reactor: exploration of multi-batch cycle length and UB4 admixture for reactivity control." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Brown, N., Todosow, M. and Cuadra, A. (2015a) "Screening of advanced cladding materials and UN–U3Si5 fuel." J. Nucl. Mat., 462 (2015) 26-42.
Brown, N., Powers, J., Feng, B., Heidet, F., Stauff, N., Zhang, G., Todosow, M., Worrall, A., Gehin, J., Kim, T. and Taiwo, A. (2015b) "Sustainable thorium nuclear fuel cycles: A comparison of intermediate and fast neutron spectrum systems." Nucl. Eng. Design, 289 (2015) 252–265.
Brown, N., Worral, A. and Todosow, M. (2017a) "Impact of thermal spectrum small modular reactors on performance of once-through nuclear fuel cycles with low-enriched uranium." Ann. Nucl. Energy, 101 (2017) 166-173.
Brown, N., Betzler, B., Carbajo, J., Wysocki, A., Greenwood M., Gentry, C. and Qualls, A. (2017b) "Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis." Ann. Nucl. Energy, 103 (2017) 49-59.
Buiron, L., Rimpault, G., Fontaine, B., Kim, T., Stauff, N., Taiwo, T., Yamaji, A., Gulliford, J., Fridmann, E., Pataki, I., Keresztúri, A., Tóta, Á. Kugo, K., Sugino, K., Uematsu, M., Lin Tan, R., Kozlowski, T., Parisi, C. and Ponomarev, A. (2014) "Evaluation if Large 3600 MWth Sodium-Cooled Fast Reactor OECD Neutronic Benchmarks." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Cai, L., Pénéliau, Y., Tommasi, J., Vidal, J. and Diop, C. (2014) "Leakage-corrected fast reactor assembly calculation with Monte-Carlo code TRIPOLI4 and its validation methodology." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Ćalić, D., Trkov, A. and Kromar, M. (2012a) "Neutron multigroup homogenized cross section determination with the Monte Carlo method." In proc. 21st International Conference Nuclear Energy for New Europe 2012, Ljubljana, Slovenia, Sept. 5-7, 2012.
Ćajko, F., Sećansky, M., Chrebet, T., Zajac, R. and Darilek, P. (2016) "Neutronic analysis of absorbing materials for the control rod system in reactor ALLEGRO." Kerntechnik, 81 (2016) 445-451.
Ćalić, D., Trkov, A. and Kromar, M. (2012b) "Parallelisation of burnup calculations performed with Monte Carlo code Serpent." In proc. 21st International Conference Nuclear Energy for New Europe 2012, Ljubljana, Slovenia, Sept. 5-7, 2012.
Ćalić, D., Kromar, M. and Trkov, A. (2014) "Effective Diffusion Homogenization of Cross Sections With the Monte Carlo Method." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Ćalić, D., Trkov, A., Kromar, M. and Snoj, L. (2016a) "Use of Effective Diffusion Homogenization method with the Monte Carlo code for light water reactor." Ann. Nucl. Energy, 94 (2016) 392-398.
Ćalić, D. and Trkov, A. (2016b) "Monte Carlo Simulation on Krško NPP." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Ćalić, D., Zerovnik, G., Trkov, A. and Snoj, L. (2016c) "Validation of the Serpent 2 code on TRIGA Mark II benchmark experiments." Appl. Radiat. Isot., 107 (2016) 165-170.
Canbakan, A., Hébert, A. and Vidal, J. (2015) "Accuracy of a Subgroup Method for Pressurized Water Reactor Fuel Assembly Models." In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
Canepa, S., Hursin, M., Ferroukhi, H. and Pautz, A. (2013) "Preparation of nuclear libraries with deterministic and stochastic methods for for LWR reflectors." In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
Cheng, Y. and Roberts, J. (2016) "Impact of Spatial Discretization on Reactivity Biases in Depleted TRIGA Fuel." Trans. Am. Nucl. Soc., 115 (2016) 1160-1162.
Chersola, D., Lomonaco, G., Marotta, R. and Mazzini, G. (2014a) "Comparison between SERPENT and MONTEBURNS codes applied to burnup calculations of a GFR-like configuration." Nucl. Eng. Design, 273 (2014) 542–554.
Chersola, D., Lomonaco, G., and Mazzini, G. (2014b) "Cross sections influence on Monte Carlo based burnup codes." In proc. ICONE22, Prague, Czech Republic, Jul. 7-11, 2014.
Chersola, D., Lomonaco, G. and Mazzini, G. (2015) "Cross-Section Influence on Monte Carlo-Based Burn-Up Codes Applied to a GFR-Like Configuration." ASME J. of Nuclear Rad Sci., 1 (2015) 031004.
Chersola, D., Mazzini, G., Kostál, M., Miglierini, B., Hrehor, M., Lomonaco, G., Borreani, W. and Ruscák, M. (2016) "Application of Serpent 2 and MCNP6 to study different criticality configurations of a VVER-1000 mock-up." Ann. Nucl. Energy, 94 (2016) 109-122.
Colak, U. and Turkmen, M. (2011) "The Effect of Neutron Energy Spectrum on Actinide Management in High Temperature Reactors." In proc. 20th International Conference Nuclear Energy for New Europe 2011, Bovec, Slovenia, Sept. 12-15, 2011.
Daeubler, M., Jimenez, J. and Sanchez, V. (2014a) "Generation and Application of Interface Discontinuity Factors in the Reactor Simulator DYN3D." In proc. ICAPP 2014, Charlotte, NC, Apr. 6-9, 2014.
Daeubler, M., Jimenez, J. and Sanchez, V. (2014b) "Development of a High-Fidelity Monte Carlo Thermal-Hydraulics Coupled Code System Serpent/SUBCHANFLOW -- First Results." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Daeubler, M., Ivanov, A., Sjenitzer, B., Sanchez, V., Stieglitz, R. and Macian-Juan, R. (2015) "High-fidelity coupled Monte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW." Ann. Nucl. Energy, 83 (2015) 325-375.
da Cruz, D. (2016) "Uncertainty due to Nuclear Data for an MTR Fuel Assembly." Trans. Am. Nucl. Soc., 115 (2016) 1357-1359.
Darnowski, P., Potapczyk, K., Gatowski, M. and Niewinsk, G. (2016) "Development of one-way-coupling methodology between severe accident integral code MELCOR and Monte Carlo neutron transport code SERPENT." Procedia Engineering, 157 (2016) 207-213.
Darnowski, P., Potapczyk, K. and Swirski, K. (2017) "Investigation of the recriticality potential during reflooding phase of Fukushima Daiichi Unit-3 accident." Ann. Nucl. Energy, 99 (2017) 495-509.
Davidson, G., Pandy, T., Isotalo, A., Johnson, S., Evans, T. and Wieselquist, W. (2016) "Nuclide Depletion Capabilities in the SHIFT Monte Carlo Code." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
DeHart, M. and Bowman, S. (2011) "Reactor Physics Methods and Analysis Capabilities in SCALE." Nucl. Sci. Eng., 174 (2011) 196-213.
DeHart, M., Goluoglu, S. and Leppänen, J. (2009) "A Comparison of Deterministic and Monte Carlo Depletion Methods for HTGR Fuel Elements." Trans. Am. Nucl. Soc., 101 (2009) 778-781.
DeHart, M., Pope, M., Nigg, D., Jamison, R. and Morrell, S. (2013) "Fuel element design and analysis for Advanced Test Reactor conversion to LEU fuel." Trans. Am. Nucl. Soc., 109 (2013) 1343-1347.
DeHart, M., Ortensi, J., Baker, B., Gleicher, F., Wang, Y. and Schunert, S. (2016) "Research in Support of TREAT Kinetics Calculations Using RattleSNake/Bison Coupling Within Mammoth." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Demazičre, C. (2016) "Investigation of the Bias Coming From Spectrum Corrections in the Simulations of Nuclear Reactor Transients." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Duerigen, S. and Fridman, E. (2012) "The simplified P3 approach on a trigonal geometry of the nodal reactor code DYN3D." Kerntechnik, 77 (2012) 226-229.
Dufek, J., Kotlyar, D., Shwageraus, E. and Leppänen, J. (2013b) "Numerical stability of the predictor-corrector method in Monte Carlo burnup calculations of critical reactors." Ann. Nucl. Energy, 56 (2013) 34-38.
Dulla, S., Nervo, M., Ravetto, P. and Carta, M. (2013) "Spatial and Spectral Effects in Subcritical System Pulsed Experiments." In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
Eades, M. and Venneri, P. (2016) "Xenon-135m in Nuclear Thermal Propulsion." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Eades, M., Chaleff, E., Venneri, P. and Blue, T. (2017) "The influence of Xe-135m on steady-state xenon worth in thermal molten salt reactors." Prog. Nucl. Energy, 93 (2016) 397-405.
Elsawi, M. and Alnoamani, Z. (2016) "Neutronic Analysis of the APR1400 Reactor Core with SCALE and Serpent Reactor Physics Codes - Power Distribution." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Faure, B. and Marleau, G. (2017) "Simulation of a sodium fast core: Effect of B1 leakage models on group constant generation." Ann. Nucl. Energy, 99 (2017) 484-494.
Fei, T., Vezzoni, B., Marchetti, M., van Rooijen, W. and Zhang Y. (2016) "Neutronics Benchmark for EBR-II Shutdown Heat Removal Test SHRT-45R." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Fejt, F. (2015) "CUDA-Accelerated Algorithm in 3D Neutron Diffusion Calculation at the VR-1." Trans. Am. Nucl. Soc., 113 (2015) 1602-1605.
Ferraro, D. and Villarino, E. (2011a) "Calculations for a BWR lattice with adjacent gadolinium pins using the Monte Carlo cell code Serpent v.1.1.7." Sci. Technol. Nucl. Install., 2011 (2011), Article ID 659406.
Ferraro, D. and Villarino, E. (2011b) "OPAL reactor calculations using the Monte Carlo code Serpent." In proc. 4th International Symposium on Material Testing Reactors, Oarai, Japan, Dec. 5-9, 2011.
Ferraro, D., Cuello E. and Sardella, F. (2013) "Low Power Research Reactor Calculations using Deterministic and Stochastical Transport Codes." In proc. 6th International Symposium on Material Testing Reactors (ISMTR), Bariloche, Argentina, Oct. 28-31, 2013.
Ferraro, D., Villarino, E. (2014) "OPAL Reactor Full 3-D Calculations using the Monte Carlo Code Serpent 2." In proc. 16th International Group on Research Reactor (IGORR), Bariloche, Argentina, Nov. 17-21, 2014.
Ferraro, D., Villarino, E. (2016) "Full 3-D core calculations with refueling for the OPAL Research Reactor using Monte Carlo Code Serpent 2." Ann. Nucl. Energy, 92 (2016) 369-377.
Fiorina, C., Aufiero, M., Cammi, A., Franceschini, F., Krepel, J., Luzzi, L., Mikityuk, K. and Ricotti, M. E. (2013) "Investigation of the MSFR core physics and fuel cycle characteristics." Prog. Nucl. Energy, 68 (2013) 153-168.
Fiorina, C., Lathouwers, D., Aufiero, M., Cammi, A., Guerrieri, C., Kloosterman, J. L., Luzzi, L. and Ricotti, M. E (2014) "Modelling and analysis of the MSFR transient behaviour." Ann. Nucl. Energy, 64 (2014) 485-498.
Fiorina, C., Mikityuk, K. and Pautz, A. (2015) "GeN-Foam: A Novel Multi-Physics Solver for Reactor Analysis – Status and Ongoing Developments." Trans. Am. Nucl. Soc., 113 (2015) 1132-1134.
Fiorina, C., Clifford, I., Aufiero, M., Mikityuk, K. (2015) "GeN-Foam: a novel OpenFOAM based multi-physics solver for 2D/3D transient analysis of nuclear reactors." Nucl. Eng. Design, 294 (2015) 24-37.
Fiorina, C. and Pautz, A. (2016) "Status and Ongoing Developments for the GeN-Foam Multi-Physics Solver." Trans. Am. Nucl. Soc., 115 (2016) 1106-1109.
Fiorina, C., Hursin, M. and Pautz, A. (2017) "Extension of the GeN-Foam neutronic solver to SP3 analysis and application to the CROCUS experimental reactor." Ann. Nucl. Energy, 101 (2017) 419-428.
Franceschini, F., Salazar, D., Ouisloumen, M., Godfrey, A., Stimpson, S., Collins, B. and Gentry, C. (2016) "AP1000 PWR Cycle 1 HFP Depletion Simulations with VERA-CS." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Fratoni, M. and Terrani, K. (2012) "Metal Matrix Microencapsulated (M3) fuel neutronics performance in PWRs." Trans. Am. Nucl. Soc., 107 (2012) 1025-1028.
Fridman, E. and Shwageraus, E. (2012b) "Demonstration of the Serpent Monte-Carlo Code Applicability to Few-Group Constants Generation for Existing and Advanced Reactor Concepts." In proc. 26th Conference of the Nuclear Societies in Israel, Dead Sea, Israel, Feb. 21-23, 2012.
Fridman, E. and Shwageraus, E. (2013a) "Modeling of SFR cores with Serpent-DYN3D codes sequence." Ann. Nucl. Energy, 53 (2013) 354-363.
Fridman, E., Duerigen, S., Bilodid, Y., Kotlyar, D. and Shwageraus, E. (2013b) "Axial discontinuity factors for the nodal diffusion analysis of high conversion BWR cores." Ann. Nucl. Energy, 62 (2013) 129-136.
Fridman, E., Leppänen, J. and Wemple, C. (2013c) "Comparison of Serpent and HELIOS-2 as applied for the PWR few-group cross section generation." In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
Fridman, E., Rachamin, R. and Shwageraus, E. (2013d) "Generation of SFR few-group constants using the Monte Carlo code Serpent." In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
Fridman, E. (2013e) "Serpent Monte-Carlo-Code: An Advanced Tool for Few-Group Cross Section Generation." ATW, 58 (2013) 156-157.
Galchenko, V., Gulik, V. and Shlapak, I. (2016) "Using of the Serpent code based on the Monte-Carlo method for calculation of the VVER-1000 fuel assembly characteristics." Nuclear Physics and Atomic Energy, 3 (2016) 250-258. (in Ukranian)
Gentry, C., George, N., Chvala, O., Maldonado, G. I., Lewis, S., Avigni, P. and Petrovic, B. (2013) "Core physics parametric studies for liquid salt cooled reactors." Trans. Am. Nucl. Soc., 108 (2013) 831-833.
Gentry, C., Maldonado, I. and Chvala, O. (2015) "Burnable Poison Reactivity Control for the Advanced High Temperature Reactor." Trans. Am. Nucl. Soc., 113 (2015) 1265-1267.
Gentry, C., Maldonado, I. and Kim, K. (2016) "Development of Two-step Reactor Physics Analysis Procedure for Advanced High Temperature Reactors." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
George, N., Gentry, C., Chvala, O. and Maldonado, G. I. (2013) "Two dimensional calculations for liquid salt cooled reactors." Trans. Am. Nucl. Soc., 109 (2013) 1339-1342.
Gleicher, F., Ortensi, J., Spencer, B., Wang, Y., Novascone, S., Hales, J., Gaston, D., Williamson, R. and Martineau, R. (2014) "The Coupling of the Neutron Transport Application RattleSNake to the Nuclear Fuels Performance Application Bison Under the Moose Framework." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Gleicher, F., DeHart, M., Ortensi, J., Wang, Y., Alberti, A and Palmer, T. (2015) "Development of Multi-Physics Methods to Support Restart of the Transient Test Reactor." Trans. Am. Nucl. Soc., 112 (2015) 711-712.
Glinatsis, G. and Gugiu, D. (2013) "Coolant void effect investigation case of a Na-cooled fast reactor." J. Nucl. Research and Devel., 6 (2013) 13-18.
Godfrey, A., Jessee, M., Stimpson, S., Collins, B., Evans, T., Kromar, M., Franceschini, F. and Salazar, D. (2016) "VERA Benchmarking Results for Krško Nuclear Power Plant Cycle 1." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Gómez Torres, A., Delfín Loya, A. and del Valle Gallegos, E. (2012) "Generación de secciones eficaces y soluciones de referencia usando el código Serpent." In proc. XXIII Congreso Anual de la SNM, Oaxaca, México, Jul. 29 - Aug. 1, 2012 (in Spanish).
Grgic, D., Jecmenica, R. and Pevec, D. (2012) "Lattice codes pin power prediction comparison." Nucl. Eng. Design, 246 (2012) 27-40.
Guillard, N., Bernnat, W., Starflinger, J., Zwermann, W. and Pasichnyk, I. (2014) "Monte Carlo Neutronics Analysis of Sodium-Cooled Fast Reactor Benchmark with Temperature and Burnup Treatment." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Guilliard, N., Bernnat, W., Lapins, J., Pasichnyk, I., Perin, Y., Velkov, K. and Zwermann, W. (2016) "Analysis of Large Core Neutronics by the Monte Carlo Method Coupled with Thermal Hydraulics." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Gulik, V., Pavlovych, V. and Tkaczyk, A. (2013a) "Using SERPENT Monte Carlo and Burnup code to model Traveling Wave Reactors (TWR)." In proc. SNA + MC 2013, Paris, France, Oct. 27-31, 2013.
Gulik, V. and Tkaczyk, A. (2013b) "Optimization of geometry, material and economic parameters of a two-zone subcritical reactor for transmutation of nuclear waste with SERPENT Monte Carlo code." In proc. SNA + MC 2013, Paris, France, Oct. 27-31, 2013.
Gulik, V. and Tkaczyk, A. (2014a) "Cost optimization of ADS design: Comparative study of externally driven heterogeneous and homogeneous two-zone subcritical reactor system." Nucl. Eng. Design, 270 (2014) 133-142.
Gulik, V., Pavlovych, V. and Tkaczyk, A. (2014b) "About possibility of analysis of wave passing in Traveling Wave Reactors (TWR) with help of Monte Carlo method." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Gulik, V., Pavlovych, V. and Tkaczyk, A (2014c) "The Neutron-Physical Model of Two-Zone Research Sub-Critical Reactor for Investigation of Nuclear Waste Transmutation." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Guillard, N., Bernnat, W., Starflinger, J., Zwermann, W. and Pasichnyk, I (2014) "Monte Carlo Neutronics Analysis of Sodium-Cooled Fast Reactor Benchmark with Temperature and Burnup Treatment." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Hall, A., Xu, Y., Ward, A., Downar, T., Shirvan, K. and Kazimi, M. (2013) "Advanced neutronics methods for analysis of the RBWR-AC." Trans. Am. Nucl. Soc., 108 (2013) 771-774.
Hall, A., Downar T., Ward A., Jarret M., Wysocki A., Xu Y. and Shirvan K. (2014) "Advanced Methods Development for Equilibrium Cycle Calculations of the RBWR." In proc. ICAPP 2014, Charlotte, NC, Apr. 6-9, 2014.
Haroon, J. Kicka, L., Mohapatra, S., Nichita E. and Schwanke, P. (2016) "Comparison of the Reactivity Effects Calculated by DRAGON and Serpent for a PHWR 37-Element Fuel Bundle." ASME J. of Nuclear Rad. Sci., 3 (2016) 011011.
Harrisson, G. and Marleau, G. (2012) "Computation of a Canadian SCWR unit cell with deterministic and Monte Carlo codes." In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
Harrisson, G. and Marleau, G. (2013) "Simulation strategy for the evaluation of neutronic properties of a Canadian SCWR fuel channel." Sci. Technol. Nucl. Install., 2013 (2013), Article ID 352757.
Hartanto, D., Kim, Y. and Venneri, F. (2015) "Neutronics evaluation of a super-deep-burn with TRU Fully Ceramic Microencapsulated (FCM) fuel in CANDU." Prog. Nucl. Energy, 83 (2015) 261-269.
Hébert, A. (2016) "DRAGON5 and DONJON5, the contribution of École Polytechnique de Montréal to the SALOME platform." Ann. Nucl. Energy, 87 (2016) 12-20.
Helgesson, P., Rochman, D., Sjöstrand, H., Alhassan E. and Koning, A. (2014) "UO2 Versus MOX: Propagated Nuclear Data Uncertainty for keff, with Burnup." Nucl. Sci. Eng., 177 (2014) 321-336.
Helgesson, P., Sjöstrand, H., Koning, A., Rydén, J., Rochman, D., Alhassan, E. and Pomp, S. (2017) "Combining Total Monte Carlo and Unified Monte Carlo: Bayesian nuclear data uncertainty quantification from auto-generated experimental covariances." Prog. Nucl. Energy, 96 (2017) 76-96.
Hellesen, C., Wolniewicz, P., Jansson, P., Hĺkansson, A., Svärd, S. and Österlund, M. (2014) "Transient Simulation of Gas Bubble in a Medium Sized Lead Cooled Fast Reactor." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Henrice, E., Palma, D., Gonçalves, A. and Mesquita, A. (2015) "Neutronic Flux Analysis In Subcritical Systems Using The R/S And DFA Methods." Trans. Am. Nucl. Soc., 113 (2015) 1317-1320.
Heo, W. and Kim, Y. (2016) "Position-Dependency of Fuel Assembly Homogenization in a Pressurized Water Reactor." Trans. Am. Nucl. Soc., 113 (2016) 761-764.
Herman, B., Shwageraus, E., Leppänen, J. and Forget, B. (2011) "Cross section generation strategy for advanced LWRs." In proc. ICAPP 2011, Nice, France, May 2-5, 2011.
Hernández, A., Torres, A. del Valle Gallegos, E. (2017) "HPC implementation in the time-dependent neutron diffusion code AZKIND." Ann. Nucl. Energy, 99 (2017) 174-182.
Herrero, J., Vasiliev, A., Pecchia, M., Ferroukhi, H. and Caruso, S. (2016) "Review calculations for the OECD/NEA Burn-up Credit Criticality Safety Benchmark" Ann. Nucl. Energy, 87 (2016) 48-57.
Hidayatullah, R. and Kim, Y. (2013a) "Feasibility of Coated Particle Fuel for a High-Performance, Ultra-Safe Research Reactor." In proc. Transactions of RRFM2013, Saint Petersburg, Russia, Apr. 21-25, 2013.
Hidayatullah, R. and Kim, Y. (2013b) "A Novel Plate Fuel Concept Based on Coated Particle for Research Reactor." Trans. Korean Nucl. Soc., Spring Meeting, Gwangju, Korea, May 30-31, 2013.
Hidayatullah, R. and Kim, Y. (2013c) "A new coated UO2 particle fuel for ultra-high performance research reactor." Trans. Am. Nucl. Soc., 108 (2013) 759-760.
Hidayatullah, R. and Kim, Y. (2013d) "Preliminary Study of Plate Fuel Concept Based on Coated Particle Fuel for Research Reactor." In proc. IGORR 2013 and IAEA Technical Meeting, Daejeon, Korea, Oct.r 13-18, 2013.
Hidayatullah, R., Hartanto, D. and Kim, Y. (2015) "A novel research reactor concept based on coated particle fuel" Ann. Nucl. Energy, 77 (2015) 477-486.
Hill, I., Soppera, N. and Bossant, M. (2014) "IDAT: The International Handbook of Evaluated Reactor Physics Benchmark Experiments Database and Analysis Tool" Nucl.Sci.Eng, 178 (2014) 280-294.
Hiscox, B. and Shirvan, K. (2016) "Neutronics Analysis of Fuel-in-fiber Concept." Trans. Am. Nucl. Soc., 115 (2016) 1351-1354.
Holt, L., Schubert, A., Van Uffelen, P., Walker, C., Fridman, E. and Sonoda, T. (2014) "Sensitivity study on Xe depletion in the high burn-up structure of UO2." J. Nucl. Mat., 452 (2014) 166-172.
Hou, J., Heidet, F., Gorman, P. and Greenspan, E. (2014) "On Multi-Group Cross Sections for Breed-and-Burn Reactors." Trans. Am. Nucl. Soc., 111 (2014) 1267-1270.
Hou, J., Choi, H. and Ivanov, K. (2015) "Development of an iterative diffusion-transport method based on MICROX-2 cross section libraries." Ann. Nucl. Energy, 77 (2015) 335-342.
Hursin, M., Vasiliev, A., Ferroukhi, H. and Pautz, A. (2013) "Comparison of Serpent and CASMO-5M for pressurized water reactors models." In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
Hursin, M., Rossinelli, L., Ferroukhi, H. and Pautz, A. (2015) "BWR Full Core Analysis with Serpent/Simulate-3 Hybrid Stochastic/Deterministic Code Sequence." In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
Hussein, M., Lewis, N. and Bonin, H. (2013) "Numerical verification/validation of the theory of coupled reactors for deuterium critical assembly, using MCNP5 and Serpent codes." In proc. 12th International Conference on CANDU Fuel, Kingston, ON, Canada, Sept. 15-18, 2013.
Hussein, M., Bonin, H., Lewis B. and Chan P. (2015) "Design of a Multi-Spectrum CANDU-Based Reactor, MSCR, With 37-Element Fuel Bundles Using SERPENT Code." In proc. 7ICMSNSE, Ottawa, ON, Oct. 18-21, 2015.
Ilas, G, Gauld, I., Sunny, E., Westfall, M. and Nguyen, J. (2015) "Modeling and Simulation of Hanford B Reactor Experiments." In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
Ipbüker, C., Nulk, H., Gulik, V., Biland, A. and Tkaczyk, A. (2015) "Radiation shielding properties of a novel cement–basalt mixture for nuclear energy applications." Nucl. Eng. Design, 284 (2015) 27-37.
Jareteg, K., Vinai, P. and Demaziére, C. (2013) "Investigation of the possibility to use a fine-mesh solver for resolving coupled neutronics and thermal-hydraulics." In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
Jareteg, K., Vinai, P. and Demaziére, C. (2014a) "Fine-mesh deterministic modeling of PWR fuel assemblies: Proof-of-principle of coupled neutronic/thermal–hydraulic calculations." Ann. Nucl. Energy, 68 (2014) 247–256.
Jareteg, K., Vinai P., Demazičre, C. and Sasic, S. (2014b) "Influence of an SN Solver in a Fine-Mesh Neutronics/Thermal-Hydraulics Framework." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Johns, J. and Tsvetkov, P. (2012) "Autonomous corium reactor for terrestrial applications." In proc. ICONE20, Anaheim, CA, Jul. 30 - Aug. 3, 2012.
Johns, J., Valtavirta, V. and Lenard, R. (2015) "Dynamic Simulation of Nuclear Reactors Experiencing High Rates of Deformation." Trans. Am. Nucl. Soc., 112 (2015) 711-712.
Juutilainen, P. (2008) "Simulating the behaviour of the fast reactor JOYO." In proc. IYNC-2008, Interlaken, Switzerland, Sept. 20-26, 2008.
Kasselmann, S., Schitthelm, O., Tantillo, F., Scholthaus, S., Rössel, C. and Allelein, H. (2016) "Development of a new nuclide generation and depletion code using a topological solver based on graph theory." Nucl. Eng. Design, 306 (2016) 154-159.
Kasselmann, S., Xhonneux, A., Tantillo, F., Trabadela, A., Lambertz, D. and Allelein, H. (2016) "V&V of the HTR Code Package (HCP) as a comprehensive HTR steady state and transient safety analysis framework." In proc. HTR 2016, Las Vegas, NV, Nov. 6-10, 2016.
Kelsey, J., Morell-Pacheco, A., Hughes, T., Whitman, N. and Tsvetkov, P. (2016) "VASIMR Interfaced High Temperature Gas-Cooled Fast Reactor for Space Applications." Trans. Am. Nucl. Soc., 115 (2016) 80-83.
Kim, J. and Kim, Y. (2015) "Xe-135m Impact on the PCR Measurement of CANDU6 Core." Trans. Am. Nucl. Soc., 112 (2015) 682-684.
Kim, J., Kim Y. and Kim, K. (2015) "Modelling of Xe-135m for Evaluation of the CANDU6 Power Coefficient of Reactivity." In proc. 7ICMSNSE, Ottawa, ON, Oct. 18-21, 2015.
Kim, K., Hu, J. and Gentry, C. (2016) "Embedded Self-Shielding Method Applied to Doubly Heterogeneous Fully Ceramic Micro-Encapsulated Fuels." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Kim, S., Oh, B., Cho, S., Baik, S., You, H., Moon, J. and Lee, J. (2016) "Conceptual System Design of a Supercritical CO2 cooled Micro Modular Reactor." In proc. HTR 2016, Las Vegas, NV, Nov. 6-10, 2016.
Kim, W., Hartanto, D. and Kim, Y. (2012) "Comparative Evaluation of Fuel Temperature Coefficient of Standard and CANFLEX Fuels in CANDU 6." Trans. Korean Nucl. Soc., Autumn Meeting, Gyeongju, Korea, Oct. 25-26, 2012.
Kim, W. and Kim, Y. (2013b) "Improvement of Safety Parameters by Using Erbium-loaded CANFLEX Fuel Bundle in the CANDU Reactor." In proc. ICAPP 2013, Jeju, Korea, Apr. 14-18, 2013.
Kim, W. and Kim, Y. (2013c) "Application of the 3-D Nodal Equivalence Theory to the CANDU Reactor." Trans. Korean Nucl. Soc., Spring Meeting, Gwangju, Korea, May 30-31, 2013.
Kim, W. and Kim, Y. (2013d) "A Novel Utilization of Er Burnable Absorber for Improvement of CANDU Safety Parameters." Trans. Am. Nucl. Soc., 108 (2013) 714-715.
Kim, W., Park, J. Kozlowski, T. Lee, Y. and Lee, D. (2015) "Comparative Neutronics Analysis of DIMPLE S06 Criticality Benchmark with Contemporary Reactor Core Analysis Computer Code Systems" Sci. Technol. Nucl. Install., 2015 (2015), Article ID 180979.
Kim, W., Motalab, M., Bae, J. and Kim, Y. (2016) "mprovement of CANDU safety parameters by using the CANFLEX fuel." Ann. Nucl. Energy, 94 (2016) 793-801.
Kim, W., Reitsma, F. and Lee, D. (2016) "IAEA Coordinated Research Program on HTGR Uncertainty Analysis: Results of Exercise I-1 Model and the Application of the RPT Method." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Kloosterman, J., Huisman M. and Rohde M. (2014) "Preliminary Design of the Delft Isotope Production Reactor (DIPR)." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Knebel, M., Mercatali, L., Sanchez, V., Stieglitz, R. and Macian-Juan, R. (2016) "Validation of the Serpent 2-DYNSUB code sequence using the Special Power Excursion Reactor Test III (SPERT III)." Ann. Nucl. Energy, 91 (2016) 79-91.
Kochetkov, A., Krása, A., Vittiglio, G., Wagemans, J., Bianchini, A., Fabrizio, V., Carta, M. Firpo, G., Fridman, E., Sarotto, M. and Bécares, V. (2016) "Spectrun Index and Minor Actinide Fission Rate Measurements in Several Fast Lead Critical Cores in the Zero Power VENUS-F Reactor." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Kodeli, I., Aufiero, M. and Zwermann, W. (2016a) "Comparison of Deterministic and Monte Carlo codes SUSD3D, Serpent AND XSUSA for Beta-effective Sensitivity Calculations." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Kodeli, I., Mastrangelo, V., Ivanov, E., Aures, A., Zwermann, W., Aufiero, M., Peneliau, Y., Ivanov, K. and Sartori, E. (2016b) "OECD/NEA Intercomparison of Deterministic and Monte Carlo Cross-section Sensitivity Codes Using SNEAK-7 Benchmarks." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Korkmaz, M., Yigit, M. and Agar, O. (2013) "Burnup calculations using Serpent code in accelerator driven thorium reactors." Kerntechnik, 78 (2013) 193-197.
Kotlyar, D. and Shwageraus, E. (2012) "Comparison of square and hexagonal fuel lattices for high conversion PWRs." Kerntechnik, 77 (2012) 292-299.
Kotlyar, D. and Shwageraus, E. (2013) "On the use of predictor-corrector method for coupled Monte Carlo burnup codes." Ann. Nucl. Energy, 58 (2013) 228-237.
Kotlyar, D., Aufiero, M., Shwageraus, E. and Fratoni, M. (2017) "A perturbation-based susbtep method for coupled depletion Monte-Carlo codes." Ann. Nucl. Energy, 102 (2017) 236-244.
Krepel, J., Hombourger, N., Fiorina, C., Mikityuk, K., Rohde, U., Kliem, S. and Pautz, A. (2014) "Fuel cycle advantages and dynamics features of liquid fueled MSR." Ann. Nucl. Energy, 64 (2014) 380-397.
Krepel, J., Mikityuk, K., Hombourger, B., Pautz, A., Zanetti, M., Aufiero, M. and Luzzi, L. (2014) "Hybrid Spectrum Molten Salt Reactor." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Kumar, A. and Tsvetkov, P. (2015a) "A new approach to nuclear reactor design optimization using genetic algorithms and regression analysis." Ann. Nucl. Energy, 85 (2015) 27-35.
Kumar, A. and Tsvetkov, P. (2015b) "Parametric Analysis and Optimization using Multivariate Regression Analysis and Genetic Algorithms." Trans. Am. Nucl. Soc., 112 (2015) 148-152.
Kumar, A. and Tsvetkov, P. (2015c) "Optimization of U–Th fuel in heavy water moderated thermal breeder reactors using multivariate regression analysis and genetic algorithms." Ann. Nucl. Energy, 85 (2015) 885-892.
Kumar, A. and Tsvetkov, P. (2016) "An Iterative Optimization Strategy for Nuclear Reactor Design." Trans. Am. Nucl. Soc., 113 (2016) 242-245.
Lahtinen, T. (2014) "Solution of the CB6 benchmark on VVER-440 final disposal using the Serpent reactor physics code." Kerntechnik, 79 (2014) 303-313.
Lajoie M., Marleau G., Martin. N. and Hébert A. (2010) "Application of 3D Collision Probability Method to VHTR Spherical Geometries." In proc. PHYSOR 2010, Pittsburgh, PA, May 9-14, 2010.
Laureau, A., Aufiero, M., Rubiolo, P., Merle-Lucotte, E. and Heuer, D. (2015a) "Coupled Neutronics and Thermal-hydraulics Transient Calculations Based on a Fission Matrix Approach: Application to the Molten Salt Fast Reactor." In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
Laureau, A., Aufiero, M., Rubiolo, P., Merle-Lucotte, E. and Heuer, D. (2015b) "Transient Fission Matrix: Kinetic calculation and kinetic parameters Β_eff and Λ_eff calculation." Ann. Nucl. Energy, 85 (2015) 1035-1044.
Lee, Y. and Cho, N. (2014) "Comparison of Two-Temperature Homogenized Model, Harmonic- and Volumetric-Average Thermal Conductivity Models on Transient Analysis of Fully Ceramic Microencapsulated Fuel." Trans. Am. Nucl. Soc., 111 (2014) 1562-1562.
Lee, Y. and Cho, N. (2015) "Steady- and transient-state analyses of fully ceramic microencapsulated fuel loaded reactor core via two-temperature homogenized thermal-conductivity model." Ann. Nucl. Energy, 76 (2015) 283-296.
Leray, O., Pecchia, M., Vasiliev, A., Ferroukhi, H., Pautz A. and Perrier, H. (2015) "Development, Verivication and Test Application of a Hybrid CASMO-5/Serpent Depletion Scheme." In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
Leray, O., Fiorito, L., Rochman, D., Ferroukhi, H., Pautz, A., Stankovskiy, A. and Van den Eynde, G. (2016) "Comparison of Fission Yield Perturbation Methodologies on Nuclide Composition for a PWR UO2 Fuel Assembly." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Li, Z., Cao, L., Wu, H., He, Q. and Shen, W. (2016) "On the improvements in neutronics analysis of the unit cell for the pebble-bed fluoride-salt-cooled high-temperature reactor." Prog. Nucl. Energy, 93 (2016) 287-296.
Liem, P., Hartanto, D. and Kim, Y. (2016) "Impact of new evaluated nuclear data libraries on core characteristics of innovative reactor designs." Prog. Nucl. Energy, 87 (2016) 74-88.
Lindley, B., Ahmad, A., Zainuddin, N. Franchescini, F. and Parks, G. (2014a) "Steady-state and transient core feasibility analysis for a thorium-fuelled reduced-moderation PWR performing full transuranic recycle." Ann. Nucl. Energy, 72 (2014) 320-337.
Lindley, B., Fiorina, C., Franchescini, F., Lahoda, E. and Parks, G. (2014b) "Thorium breeder and burner fuel cycles in reduced-moderation LWRs compared to fast reactors." Prog. Nucl. Energy, 77 (2014) 107-123.
Lindley, B. and Parks, G. (2014c) "Axially Heterogeneous Thorium Fuel Designs for Transuranic Burning in Reduced-Moderation BWRs." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Lomonaco, G., Borreani, W., Caiffi, B. and Chersola, D. "A short overview of ITER-like pulsed MCF reactors application as hybrid nuclear systems for actinides transmutation." In proc. FUNFI2, Rome, Italy, Oct. 26-28, 2014.
Lopez-Solis, R., François, J., Bastida-Ortiz, G., Becker, M. and Sánchez-Espinoza, V. (2016) "Fuel depletion analysis of a small sodium fast reactor with KANEXT and SERPENT." Ann. Nucl. Energy, 98 (2016) 26-35.
Lovecký, M., Piterka, L., Prehradný, J. and Škoda, R. (2014) " UWB1 – Fast nuclear fuel depletion code." Ann. Nucl. Energy, 71 (2014) 333-339.
Lovecký, M., Škoda, R., Hussein, M., Song, J. and Chan, P. (2015) "Burnable Absorbers in CANDU Fuel Bundle Depletion with UWB1 Code." In proc. 7ICMSNSE, Ottawa, ON, Oct. 18-21, 2015.
Lovecký, M., Škoda, R., Hussein, M., Song, J. and Chan, P. (2017) "The application of UWB1 nuclear fuel depletion code on a CANDU fuel bundle" Prog. Nucl. Energy, 90 (2016) 127-139.
Lu, Q. and Rizwan-uddin (2013) "Stability analysis of a natural circulation lead-cooled fast reactor." Trans. Am. Nucl. Soc., 109 (2013) 1723-1725.
Luciano, N., Ottinger, K., Collins, P., Gentry, C., George, N., Pawel, A., Kenner, K., Harty, S., Chvala, O., Maldonado, I. (2015) "The Nestle 3D Nodal Core Simulator: Modern Reactor Models." In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
Luzzi, L., Cammi, A., Di Marcello, V., Lorenzi, S., Pizzocri, D. and Van Uffelen, P. (2014) "Application of the TRANSURANUS code for the fuel pin design process of the ALFRED reactor." Nucl. Eng. Design, 277 (2014) 173-187.
Lyons, J., Marcum, W., Morrell, S. and DeHart, M. (2015) "Reactor Physics Scoping and Characterization Study on Implementation of TRIGA Fuel in the Advanced Test Reactor." Nucl. Technol., 189 (2015) 202-217.
Lötsch, T. (2014) "Fuel assembly burnup calculations for VVER fuel assemblies with the MONTE CARLO code SERPENT." Kerntechnik, 79 (2014) 295-302.
Mahjoub, M. and Koclas, J. (2015) "Comparative Static Simulations of a CANDU6 Cell Using Different Transport Codes." In proc. 35th Annual Conference of the Canadian Nuclear Society, Saint John, New Brunswick, Canada, May 31 - Jun. 3, 2015.
Maiorino, J., Stefani, G., Moreira, J., Rossi, P. and Santos, T. (2017) "Feasibility to convert an advanced PWR from UO2 to a mixed U/ThO2 core – Part I: Parametric studies." Ann. Nucl. Energy, 102 (2017) 47-55.
Margulis, M. and Shwageraus, E. (2014) "Conceptual Design of a Self-Sustainable Pressurized Water Reactor with Boiling Channels." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Margulis, M. and Shwageraus, E. (2015) "High conversion pressurized water reactor with boiling channels." Nucl. Eng. Design, 292 (2015) 98-111.
Margulis, M., Gilad, E. and Blaise. P. (2016a) "Monte Carlo Analysis of SNEAK-12A Core Disruption in Liquid-metal Fast Breeder Reactors - The Path for Innovative Severe Accident Studies in ZPR." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Margulis, M. and Gilad, E.(2016b) "Monte Carlo and nodal neutron physics calculations of the IAEA MTR benchmark using Serpent/DYN3D code system." Prog. Nucl. Energy, 88 (2016) 118-133.
Margulis, M., Blaise, P., Mellier, F. and Gilad, E. (2017a) "The path for innovative severe accident neutronics studies in ZPRs. part I.2 - Interpretation of SNEAK-12A experiment for core disruption in LMFBRs impact of nuclear data uncertainties on reactivity coefficients." Prog. Nucl. Energy, 96 (2017) 97-117.
Margulis, M., Blaise, P., Gabrielli, F., Gruel, A., Mellier, F. and Gilad, E. (2017b) "The path for innovative severe accident neutronics studies in ZPRs. Part I.1 - Analysis of SNEAK-12A experiments for core disruption in LMFBRs." Prog. Nucl. Energy, 94 (2017) 106-125.
Martin. N. and Hébert A. (2010) "An Investigation on the Use Of Probability Table Cross-sections in Monte Carlo Lattice Calculations." In proc. PHYSOR 2010, Pittsburgh, PA, May 9-14, 2010.
Martin, N. and Hebert, A. "A Monte Carlo Lattice Code with Probability Tables and Optimized Energy Meshes." Nucl. Sci. Eng., 167 (2011) 177-195.
Martinez, J., Cabellos, O., Diez, C., Gilfillan, F. and Barbas, A. (2011) "Isotopic prediction calculation methodologies: Application to Vandellos-II reactor cycles 7-11." In proc. M&C 2011, Rio de Janeiro, Brazil, May 8-12, 2011.
Maul, L., Braoudakis, G., Ho, M. and Yeoh G. (2016) "OPAL Reactor Calculations Using Reactor Physics Code Serpent." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Maul, L., Shen, D. and Fratoni, M.(2016) "Neutronics Code Benchmark for Fluoride-Salt-Cooled Reactors." Trans. Am. Nucl. Soc., 115 (2016) 1169-1172.
Mercatali, L., Venturini, A., Daeubler, M. and Sanchez, V. (2015) "SCALE and SERPENT solutions of the OECD VVER-1000 LEU and MOX burnup computational benchmark." Ann. Nucl. Energy, 83 (2015) 328-341.
Merk, B., Glivici-Cotruta, V., Duerigen, S., Rohde, U. and Kliem, S. (2013) "Overview of major HZDR developments for fast reactor analysis." Nucl. Eng. Design, 265 (2013) 1194-1204.
Mohamed, H., Kotlyar, D., Parks, G. and Shaposhnik, Y. (2016a) "Coupled Neutronic-thermal-hydraylic Analysis of a Small FHR Core with Pin-type Fuel Assemblies." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Mohamed, H., Lindley, B., Parks, G. and Leppänen, J. (2016b) "Neutronic Assessment of TRISO Particle Fuels in a Small Fluoride Salt-cooled High-temperature Reactor." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Motalab, M., Hartanto, D. and Kim, Y. (2014a) "Detailed Monte Carlo Evaluation of the Power Coefficient of Reactivity of CANDU Reactor." Trans. Korean Nucl. Soc., Spring Meeting, Jeju, Korea, May 29-30, 2014.
Motalab, M., Kim, W. and Kim, Y. (2014b) "Investigation of CANDU6 PCR with Detailed 3-D Monte Carlo Analysis." In proc. PHWR Safety 2014/CANSAS-2014, Ottawa, ON, Canada, Jun. 23-26, 2014.
Motalab, M., Cho, B., Kim, W., Cho, N. and Kim Y. (2015) "Serpent-COREDAX Analysis of CANDU-6 Time-Average Model." In proc. 7ICMSNSE, Ottawa, ON, Oct. 18-21, 2015.
Muniz, R. dos Santos, A., Yamaguchi, M., Rossi, P., Domingos, D., Mura, L. and Silva, A. (2016) "Neutronic analysis of a U–Mo–Al fuel and europium as burnable poison." Ann. Nucl. Energy, 92 (2016) 46-51.
Nam, S., Venneri, P., Kim, Y., Lee, J., Chang, s. and Jeong y. (2015) "Innovative concept for an ultra-small nuclear thermal rocket utilizing a new moderated reactor." Nucl. Eng. Techol., 47 (2015) 678-699.
Navarro, J. and DeHart, M. (2015) "Criticality Benchmarks for Validation of SERPENT as an ATR-LEU Conversion Reactor Physics Tool." Trans. Am. Nucl. Soc., 113 (2015) 1070-1074.
Nguyen, T., Wilkin, G. and Atfield, J. (2013) "Monte Carlo calculations applied to Slowpoke full-reactor analysis." CNL Nuclear Review, 2012, 43-46.
Nguyen, X. and Kim, Y. (2016) "A Study on Reconstruction of Intra-Pin Information in Pin-Wise Reactor Analysis." Trans. Am. Nucl. Soc., 115 (2016) 1256-1259.
Nigg, D., LaPorta, A., Nielsen, J., Parry, J., DeHart, M., Bays, S. and Skerjanc, W. (2013) "A Complex-geometry validation experiment for advanced neutron transport codes." Trans. Am. Nucl. Soc., 109 (2013) 1490-1493.
Nikitin, E., Fridman, E. and Mikityuk, K. (2015a) "Solution of the OECD/NEA neutronic SFR benchmark with Serpent-DYN3D and Serpent-PARCS code systems." Ann. Nucl. Energy, 74 (2015) 492-497.
Nikitin, E., Fridman, E. and Mikityuk, K. (2015b) "On the use of the SPH method in nodal diffusion analyses of SFR cores." Ann. Nucl. Energy, 85 (2015) 544-551.
Nikitin E. and Fridman, E. (2016) "Axial Fuel Rod Expansion Model in Nodal Code DYN3D for SFR Application." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Noh, K., Jung, K., Tak, T. and Lee, D. (2014) "BEAVRS Whole Core Benchmark Analysis Using Monte Carlo Codes." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Novak, O. and Chvala, O. (2016) "Lessons Learned from a VVER Benchmark Modeling." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Ochoa, R., Jimeneza, G. and Perez-Martin, S. (2013a) "Analysis of a Spanish energy scenario with generation IV nuclear reactors." Energy Conversion and Management, 75 (2013) 389-397.
Ochoa, R., Vázquez, M., Álvarez Velarde, F., Martín-Fuertes, F., García-Herranz, N. and Cuervo, D. (2013b) "A comparative study of Monte Carlo-coupled depletion codes applied to a sodium fast reactor design loaded with minor actinides." Ann. Nucl. Energy, 57 (2013) 32-40.
Ortensi, J., Cogliati, J., Pope, M. and Bess, J. (2010a) "Deterministic modeling of the high temperature test reactor with DRAGON-HEXPEDITE." In proc. HTR 2010, Prague, Czech Republic, Oct. 18-20, 2010.
Ortensi, J., Cogliati, J., Pope, M., Bess, J., Ferrer, R., Bingham, A. and Ougouag, A. (2010b) "Deterministic modeling of the High Temperature Test Reactor." INL/EXT-10-18969, Idaho National Laboratory, 2010.
Ortensi, J., Wang, Y., Baker, B., Schunert, S., Gleicher F., DeHart, M., Laurier, A. and Hébert, A. (2016a) "Preparation of a Neutron Transport Data Set for Simulations of the Transient Test Reactor Facility." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Ortensi, J., Schunert, S., Wang, Y., Baker, B., Gleicher, F. and DeHart M. (2016b) "A Neutron Streaming Problem to Test Rattlesnake Methods for TREAT." Trans. Am. Nucl. Soc., 115 (2016) 1389-1392.
Osborne, A., Deinert, M. (2014) "Using Spectral Shift to Reduce Radiation Damage in Breed-Burn Reactors." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Park, H., Saller, T., Seker, V. and Downar, T. (2013) "Neutronics analysis of the high temperature engineering test reactor (HTTR)." Trans. Am. Nucl. Soc., 108 (2013) 799-802.
Patel, V. and Tsvetkov, P. (2012) "Integrated multi-modular fast reactor concept design." In proc. ICONE20, Anaheim, CA, Jul. 30 - Aug. 3, 2012.
Patel, V. and Tsvetkov, P. (2013a) "Concept of a high temperature integrated multi-modular thermal reactor." Ann. Nucl. Energy, 55 (2013) 312-321.
Patel, V. and Tsvetkov, P. (2013b) "Multi-module approach to modularity in a neutronically coupled high temperature multi-modular system." Nucl. Eng. Design, 263 (2013) 411-418.
Pecchia, M., Wicaksono, D., Grimm, P., Vasilieva, A., Perret, G., Ferroukhi, H and Pautza, A. (2016) "Validation of Monte Carlo based burnup codes against LWR-PROTEUS Phase-II experimental data." Ann. Nucl. Energy, 97 (2016) 153-164.
Perko, Z., Pelloni, S., Mikityuk, K., Krepel, J., Szieberth, M., Gaëtan, G., Vrban, B., Lüley, J., Cerba, S., Halasz, M., Feher, S., Reiss, T., Kloosterman, J., Stainsby, R. and Poette, G. (2015) "Core neutronics characterization of the GFR2400 Gas Cooled Fast Reactor." Prog. Nucl. Energy, 83 (2015) 460-481.
Pope, M., Gougar, H. and Ryskamp, J. (2014) "Design Studies for a Multiple Application Thermal Reactor for Irradiation Experiments (MATRIX)." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Prévot, P., Nuttin, A., Capellan, N. and Méplan, C. (2017) "Enhancements to the Nodal Drift Method for a Rod Ejection Accident in a PWR-like mini-core with lumped thermal mode." Ann. Nucl. Energy, 101 (2017) 128-138.
Prinsloo, R., Zamonsky, O., Tomasevic, D., Erasmus, B. and Groenewald, S. (2015) "A Semi-Heterogeneous Method for On-the-fly Environmental Correction of Nodal Equivalence Parameters." In proc. M&C + SNA + MC 2015 Nashville, TN, Apr. 19-23, 2015.
Qiu, Y., Aufiero, M., Wang, K. and Fratoni, M. (2016) "Development of sensitivity analysis capabilities of generalized responses to nuclear data in Monte Carlo code RMC." Ann. Nucl. Energy, 97 (2016) 142-152.
Qvist, S. and Greenspan, E. (2012) "Inherent safety of minimum burnup breed-and-burn reactors." In proc. ICAPP 2012, Chicago, IL, Jun. 24-28, 2012.
Qvist, S. and Greenspan, E. (2013) "Automated breed-and-burn core design using the ADOPT code." In proc. ICAPP 2013, Jeju, Korea, Apr. 14-18, 2013.
Qvist, S. and Greenspan, E. (2014a) "The ADOPT code for automated fast reactor core design." Ann. Nucl. Energy, 71 (2014) 23–36.
Qvist, S. and Greenspan, E. (2014b) "An Autonomous Reactivity Control system for improved fast reactor safety." Prog. Nucl. Energy, 77 (2014) 32–47.
Qvist, S. and Greenspan, E. (2014c) "3D Shuffling in Breed and Burn Reactors." Trans. Am. Nucl. Soc., 111 (2014) 1274-1277.
Qvist, S., Hou, J. and Greenspan, E. (2015) "Design and performance of 2D and 3D-shuffled breed-and-burn cores." Ann. Nucl. Energy, 85 (2015) 93-114.
Qvist, S., Hellesen, C., Thiele, R., Dubberley, A., Gradecka, M. and Greenspan, E. (2016) "Autonomous Reactivity Control (ARC) — Principles, geometry and design process." Nucl. Eng. Design, 307 (2016) 249-274.
Qvist, S., Hellesen, C., Gradecka, M., Dubberley, A., Fanning, T., Greenspan, E. (2017) "Tailoring the response of Autonomous Reactivity Control (ARC) systems." Ann. Nucl. Energy, 99 (2017) 383-398.
Rachamin, R. and Fridman, E. (2012) "Conceptual Design of a Pressure Tube Light Water Reactor with Variable Moderator Control." In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
Rachamin, R., Wemple, C. and Fridman, E. (2013) "Neutronic analysis of SFR core with HELIOS-2, Serpent, and DYN3D codes." Ann. Nucl. Energy, 55 (2013) 194-204.
Rachamin, R. and Kliem, S. (2017) "Validation of the DYN3D-Serpent code system for SFR cores using selected BFS experiments. Part I: Serpent calculations." Ann. Nucl. Energy, 102 (2017) 158-167.
Rais, A., Siefman, D., Girardin, G., Hursin, M. and Pautz, A. (2015) "Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL." Sci. Technol. Nucl. Install., 2015 (2015), Article ID 237646.
Rais, A., Hursin, M., Perret G. and Pautz, A. (2016) "Experimental Validation of Control Rod Reactivity Worth and Fission Rate Distributions for the CROCUS Reactor." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Ramey, K and Petrovic, B. (2015a) "Power Density Uncertainties in 2D Full Core Serpent Simulations." Trans. Am. Nucl. Soc., 113 (2015) 1223-1224.
Ramey, K and Petrovic, B. (2015b) "2D Serpent Model for I2S-LWR Radial Reflector Studies." Trans. Am. Nucl. Soc., 113 (2015) 1225-1227.
Rantamäki, K., Häkkinen, S. and Anttila, M.. (2011) "Impact of cross section libraries on CASMO-4E and CASMO-4 results." Ann. Nucl. Energy, 38 (2011) 2830-2835.
Raouafi, H. and Marleau, G. (2016) "Monte Carlo Simulation of Inclined Reactivity Control Rod and Boron Poisoning for the Canadian-SCWR Supercell;." ASME J. of Nuclear Rad Sci., 2 (2016) 021015.
Read, E. (2010) "Methodology and Visualization of Monte Carlo calculation for displacements per atom in light water reactors." In proc. SNA + MC 2010, Tokyo, Japan, Oct. 17-21, 2010.
Reiter, C., Breitkreutz, H., Röhrmoser, A. and Petry, W. (2016) "First steps towards a coupled code system for transient calculations for FRM II." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Reitsma, F. and Kim, W. (2016) "The Contribution of Cross-section Uncertainties to Pebble Bed Reactor Eigenvalues Results: IAEA Cooperative Research Project Phase I Standalone Neutronics." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Richard, J., Forget, B., Forsberg, C. and Smith, K. (2015) "Design Optimization of a Fluoride Salt Cooled High Temperature Test Reactor Capable of Testing Different Salt Coolants." Trans. Am. Nucl. Soc., 113 (2015) 937-942.
Rintala, L., Aarnio, P., Clerc, S. and Salomaa, R. (2012) "Monte Carlo simulation of transmutation of TRU and long-lived FP elements in an accelerator driven system." In proc. 21st International Conference Nuclear Energy for New Europe 2012, Ljubljana, Slovenia, Sept. 5-7, 2012.
Rintala, V., Suikkanen, H., Leppänen, J. and Kyrki-Rajamäki, R. (2015) "Modeling of realistic pebble bed reactor geometries using the Serpent Monte Carlo code." Ann. Nucl. Energy, 77 (2015) 223-230.
Rochman, D., Koning, A. and Da Cruz, D. (2012) "Propagation of 235,236,238U and 239Pu nuclear data uncertainties for a typical PWR fuel element." Nucl. Technol., 179 (2012) 323-338.
Rochman, D., Zwermann, W., van der Marck, S., Koning, A., Sjöstrand, H., Helgesson, P. and Krzykacz-Hausmann, B. (2014) "Efficient use of Monte Carlo: Uncertainty propagation." Nucl. Sci. Eng., 177 (2014) 337-349.
Rochman, D., Leray, O., Hursin, M., Ferroukhi, H., Vasiliev, A., Aures, A., Bostelmann, F., Zwermann, W., Cabellos, O., Diez, C., Dyrda, J., Garcia-Herranz, N., Castro, E., van der Marck, S., Sjöstrand, H., Hernandez, A., Fleming, M., Sublet, J. and Fiorito, L. (2017) "Nuclear Data Uncertainties for Typical LWR Fuel Assemblies and a Simple Reactor Core." Nucl. Data Sheets, 139 (2017) 1-76.
Rohde, U., Kliem, S., Grundmann, U., Baier, S., Bilodid, Y., Duerigen, S., Fridman, E., Gommlich, A., Grahn, A., Holt, L., Kozmenkov, Y. and Mittag, S (2016) "The reactor dynamics code DYN3D – models, validation and applications." Prog. Nucl. Energy, 88 (2016) 170-190.
Romatoski, R., Don, S., Richard, J., Short, M., Hu L. and Forsberg, C. (2013) "Fluoride Salt-Cooled High Temperature Test Reactor Core Design." Trans. Am. Nucl. Soc., 108 (2013) 603-606.
Sartori, A., Baroli, D., Cammi, A., Chiesa, D., Luzzi, L., Ponciroli, R., Previtali, E. Ricotti, M., Rozza, G. and Sisti, M. (2014) "Comparison of a Modal Method and a Proper Orthogonal Decomposition approach for multi-group time-dependent reactor spatial kinetics." Ann. Nucl. Energy, 71 (2014) 217-229.
Sartori, A., Cammi, A., Luzzi, L. and Rozza, G. (2016) "A multi-physics reduced order model for the analysis of Lead Fast Reactor single channel." Ann. Nucl. Energy, 87 (2016) 198-208.
Scarfň, D., Caiffi, B., Chersola, D. and Lomonaco, G. (2015) "A Preliminary Assessment of the Transmutation Potentialities for an ITER-like FW Sector Loaded with MA." Global Journal of Energy Technology Research Update, 2 (2015) 52-64.
Scherr, J. and Tsvetkov, P. (2015) "Fast Spectrum Material’s Testing Reactor with Variable Energy Spectra to Support Advanced Reactors Program and Light Water Reactor Sustainability Program R&D." Trans. Am. Nucl. Soc., 113 (2015) 1115-1118.
Scherr, J. and Tsvetkov, P. (2016) "Fast Spectrum Materials Test Reactor with Variable Neutron Spectra in Support of Next Generation Nuclear Power Plant and Light Water Reactor Sustainability R&D." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Scopatz, A., Romano, P., Wilson, P. and Huff, K. (2012) "PYNE : Python for Nuclear Engineering." Trans. Am. Nucl. Soc., 107 (2012) 985-987.
Scopatz, A. and Schneider, E. (2012) "Interpolations of nuclide-specific scattering kernels generated with Serpent." In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
Sen, S., Youinou, G., Wigeland, R., Salvatores, M., Palmiotti, G., Hill, D., Henslee, P., Finck, P. and Davis, C. (2016) "A Versatile Innovative Coupled Thermal-fast Test Reactor." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Shapiro, R., Younker, I. and Fratoni, M. (2013) "Neutronic performance of accident tolerant fuels." Trans. Am. Nucl. Soc., 109 (2013) 1351-1353.
Shapiro, R., Vincenzi, M. and Fratoni, M. (2014) "Optimization of Fully Ceramic Micro-Encapsulated Fuel Assembly for PWR." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Shen, W. (2012a) "Assessment of the traditional neutron-diffusion core-analysis method for the analysis of the super critical water reactor." Ann. Nucl. Energy, 45 (2012) 1-7.
Shen, W. (2012b) "On the better performance of the coarse-mesh finite-difference method for CANDU-type reactors." Ann. Nucl. Energy, 46 (2012) 169-178.
Shen, W. (2012c) "Evaluation of the adequacy of using few-group lattice-homogenized properties for the diffusion analysis of the super critical water reactor." In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
Shen, W. (2012d) "Root-cause Analysis of the Better Performance of the Coarse-mesh Finite-difference Method for CANDU-type Reactors." In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
Shirvan K. And Kazimi M. (2012) "Nuclear Design Behaviour of Helical Cruciform Fuel Rods." In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
Siefman, D., Girardin, G., Raisa, A., Pautz, A. and Hursin, M. (2015) "Full Core modeling techniques for research reactors with irregular geometries using Serpent and PARCS applied to the CROCUS reactor." Ann. Nucl. Energy, 85 (2015) 434–443.
Silva Albarrán, L., del Valle Gallegos, E. and Gómez Torres, A. (2013) "Serpent: Una alternativa para el análisis de celdas de combustible nuclear de un BWR." In proc. XXIV Congreso Anual de la SNM, Queretaro, México, Jun. 30 - Jul. 3, 2013 (in Spanish).
Sjöstrand, H., Alhassan, E., Duan, J., Gustavsson, C., Koning, A., Pomp, S., Rochman, D. and Österlund, M. (2014) "Propagation of nuclear data uncertainties for ELECTRA burn-up calculations." Nucl. Data Sheets, 118 (2014) 527-530.
Stauff, N., Kim, T., Taiwo, T., Buiron, L., Rimpault, G., Yamaji, A., Gulliford, J., K. Lee, Y., Brun, E., Guilliard, N., Bernnat, W., Uematsu, M., Sugino, K., Kugo, T., Pataki, P., Keresztúri, A., Tóta, Á., Ponomarev, A., Messaoudi, N., Lin Tan, R. and Kozlowski, T. (2014) "Evaluation of Medium 1000MWth Sodium-Cooled Fast Reactor OECD Neutronic Benchmarks." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Suikkanen, H., Rintala, V. and Kyrki-Rajamäki, R. (2010) "An approach for detailed reactor physics modelling of randomly packed pebble beds." In proc. HTR 2010, Prague, Czech Republic, Oct. 18-20, 2010.
Suikkanen, H. (editor, 2012) "New Type Nuclear Reactors (NETNUC) 2008–2011 Final Report." Research report 23, Lappeenranta University of Technology, 2012.
Suvdantsetseg, E., Wallenius, J. and Bortot, S. (2012) "Optimization of the reactivity control drum system of ELECTRA." Nucl. Eng. Design, 252 (2012) 209-214.
Suvdantsetseg, E. and Wallenius, J. (2014a) "An assessment of prompt neutron reproduction time in a reflector dominated fast critical system: ELECTRA." Ann. Nucl. Energy, 71 (2014) 159–165.
Talamo, A. and Gohar, Y. (2015) "Monte Carlo Analyses of the Yalina Thermal Facility with Serpent Stereolithography Geometry Model." In proc. AccApp ’15, Washington, DC, Nov. 10-13, 2015.
Talamo, A., Gohar, Y., Zhong, Z., Sikorin, S., Mandzik, S., Polazau, S., Hryharovich, T. and Holubeva, I. (2016a) "Serpent Stereolithography Modeling of the GIACINT Critical Assembly Experimental Facility." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Talamo, A., Gohar, Y. and Leppänen, J. (2016b) "Mesh Adaptive Search Optimization in SERPENT2 Stereolithography Geometry." Trans. Am. Nucl. Soc., 115 (2016) 1127-1129.
Templeton, J., Ortega M. and de Oliveira, C. (2014) "Three-Dimensional Modeling of the Physics of the Transient Reactor Test (TREAT) Facility." Trans. Am. Nucl. Soc., 111 (2014) 1303-1305.
Tesinsky, M., Zhang, Y. and Wallenius, J. (2012a) "The impact of americium on the ULOF and UTOP transients of the European lead-cooled system (ELSY)." Ann. Nucl. Energy, 47 (2012) 104-109.
Tesinsky, M., Wallenius, J., Jolkkonen, M. and Zhang, Y. (2012b) "The impact of americium on transients in the European lead-cooled system ELSY loaded with nitride fuel." Ann. Nucl. Energy, 50 (2012) 50-62.
Trinh, K., Parks, G., Kotlyar, D. and Fiorina, C. (2016) "Fuel Cycle Analysis of Multi-batch Operation of a Denatured Molten Salt Reactor." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Tuominen, R., Valtavirta, V., Peltola, J. and Leppänen, J. (2016) "Coupling Serpent and OpenFOAM for Neutronics - CFD Multi-physics Calculations." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Vanhanen, R. (2014) "Uncertainty analysis of infinite homogeneous lead and sodium cooled fast reactors at beginning of life." Nucl. Eng. Design, 283 (2015) 168-174.
Venneri, P., Nam, S. and Kim, Y. (2014) "Neutronics Study of the KANUTER Space Propulsion Reactor." Trans. Korean Nucl. Soc., Spring Meeting, Jeju, Korea, May 29-30, 2014.
Venneri, P and Kim, Y. (2015) "Extreme Performance Multibatch Research Reactor Based on Simple Plate Fuel." Trans. Am. Nucl. Soc., 113 (2015) 1067-1069.
Verma, V., Filliatre, P., Hellesen, C., Jacobsson Svärdb, S and Jammes, C. (2016) "Neutron flux monitoring with in-vessel fission chambers to detect an inadvertent control rod withdrawal in a sodium-cooled fast reactor." Ann. Nucl. Energy, 94 (2016) 487-493.
Wallenius, J. and Fokau, A. (2009) "A low power fast reactor cooled by natural circulation of LBE." In proc. Global 2009, Paris, France, Sept. 6-11, 2009.
Wallenius, J., Suvdantsetseg, E. and Fokau, A. (2012) "ELECTRA: European lead-cooled training reactor." Nucl. Technol., 177 (2012) 303-313.
Wallenius, J., Bortot, S. and Suvdantsetseg, E. (2013) "ELECTRA-FORTE, A really small SMR for the Canadian market." Trans. Am. Nucl. Soc., 109 (2013) 2258-2260.
Wang, L., Guo, J., Li, F., Hou, J. and Ivanov, K. (2016) "Effect of Double Heterogeneity Treatment on Neutronics Modeling of HTGR Unit Cell." In proc. HTR 2016, Las Vegas, NV, Nov. 6-10, 2016.
Ward, A., Hall, A. and Downar, T. (2014) "A Preliminary Analysis of the Accuracy of Homogenized 2D Cross Sections in 3D Nodal Calculations for BWRs." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Wicaksono, D., Grimm, P., Vasiliev, A., Hursin, M., Perret, G. and Ferroukhi, H. (2014) "Validation of Two Monte Carlo Codes for LWR Burnup Calculations." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Wolniewicz, P., Hellesen, C., Håkansson, A., Jacobsson Svärd, S. J., Jansson, P. and Österlund, M. (2013a) "Detecting neutron spectrum perturbations due to coolant density changes in a small lead-cooled fast nuclear reactor." Ann. Nucl. Energy, 58 (2013) 102-109.
Wolniewicz, P., Håkansson, A., Jansson, P, Jacobsson Svärd, S. (2013b) "Feasibility study of detection of coolant void in liquid metal cooled fast reactors using changes in the neutron spectrum." Nucl. Eng. Design, 265 (2013) 1255-1265.
Wolniewicz, P., Håkansson and Jansson, P. (2015) "Detection of coolant void in lead-cooled fast reactors." Ann. Nucl. Energy, 85 (2015) 1096-1103.
Wooten, D. and Fratoni, M. (2016) "Enhanced Fidelity Depletion for Molten Salt Reactors." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Wu, X. and Kozlowski, T. (2014) "Uncertainty quantification for coupled Monte Carlo and thermal-hydraulics codes." Trans. Am. Nucl. Soc., 110 (2014) 189-191.
Wu, X. and Kozlowski, T. (2014) "Development of a New Convergence Criterion for Monte Carlo Simulation with Thermal-Hydraulics Feedback." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Wu, X. and Kozlowski, T. (2015a) "Coupling of system thermal–hydraulics and Monte-Carlo code: Convergence criteria and quantification of correlation between statistical uncertainty and coupled error." Ann. Nucl. Energy, 75 (2015) 377-387.
Wu, X., Kozlowski, T. and Hales, J. (2015b) "Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions." Ann. Nucl. Energy, 85 (2015) 763-775.
Wyant, T. and Petrovic, B. (2012b) "Numerical study of error propagation in Monte Carlo depletion simulations." In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
Wyant, T. and Petrovic, B. (2013) "Uncertainty propagation in full-core Monte Carlo depletion simulations using Serpent." In proc. M&C 2013, Sun Valley, ID, May 5-9, 2013.
Yahya, M., Kim, Y. and Chung, C. (2014a) "A Novel Burnable Absorber Concept for PWR: BigT (Burnable Absorber-Integrated Guide Thimble)." Trans. Korean Nucl. Soc., Spring Meeting, Jeju, Korea, May 29-30, 2014.
Yahya, M., Yu, H. and Kim, Y. (2014b) "A Burnable Absorber-Integrated Control Rod Guide Thimble for PWR." Trans. Am. Nucl. Soc., 110 (2014) 593-594.
Yahya, M., Yu, H. and Kim, Y. (2014c) "BigT: a New Burnable Absorber Concept for PWR." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Yahya, M. and Kim, Y. (2014d) "Application of the BigT Burnable Absorber to AP1000 Core for a Soluble Boron Free Operation." Trans. Am. Nucl. Soc., 111 (2014) 1208-1210.
Yahya, M. and Kim, Y. (2015a) "Application of the BigT Burnable Absorber to AP1000 First Core." Trans. Am. Nucl. Soc., 112 (2015) 811-813.
Yahya, M., Hartanto D. and Kim, Y. (2015b) "A Neutronics Study on Annular Fuel Filled with Burnable Absorber." Trans. Am. Nucl. Soc., 113 (2015) 1262-1264.
Yahua, M. Kim, Y. and Chung, C. (2016) "Criticality Control of a High-Performance Soluble-Boron-Free Small Modular Reactor Core." Trans. Am. Nucl. Soc., 115 (2016) 1184-1185.
Younker, I. and Fratoni, M. (2016) "Neutronic evaluation of coating and cladding materials for accident tolerant fuels." Prog. Nucl. Energy, 88 (2016) 10-18.
Yu, H., Kim, Y. and Kim, H. (2014a) "Application of the BigT Burnable Absorber to an OPR1000 Core." Trans. Korean Nucl. Soc., Spring Meeting, Jeju, Korea, May 29-30, 2014.
Yu, H., Yahya, M. and Kim, Y. (2014b) "Application of the BigT Burnable Absorber to a Soluble Boron-free PWR Core." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Yu, H., Hartanto, D., Moon, J. and Kim, Y. (2014c) "A Conceptual Study of a Supercritical CO2 -Cooled Micro Modular Reactor." In proc. HTR-2014, Weihai, China, Oct. 27-31, 2014.
Zanetti, M., Luzzi, L., Cammi, A., Fiorina, C. (2014) "An Innovative Approach to Dynamics Modeling and Simulation of the Molten Salt Reactor Experiment." In proc. PHYSOR 2014, Kyoto, Japan, Sep. 28 - Oct. 3, 2014.
Zanetti, M., Cammi, A., Fiorina, C. and Luzzi, L. (2015) "A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics." Prog. Nucl. Energy, 83 (2015) 82-98.
Zhang, Y. and Wallenius, J. (2009) "Upper Limits to Americium Concentration in Medium Size Sodium Cooled Fast Reactors." In proc. Global 2009, Paris, France, Sept. 6-11, 2009.
Zhang, Y., Wallenius, J. and Fokau, A. (2010) "Transmutation of americium in a medium size sodium cooled fast reactor design." Ann. Nucl. Energy, 37 (2010) 629-638.
Zhang, Y., Wallenius, J. and Jolkkonen, M. (2013) "Transmutation of americium in a large sized sodium-cooled fast reactor loaded with nitride fuel." Ann. Nucl. Energy, 53 (2013) 26-34.
Zhang, Y. and Wallenius, J. (2014) "Upper limits to americium concentration in large sized sodium-cooled fast reactors loaded with metallic fuel." Ann. Nucl. Energy, 70 (2014) 180–187.
Zhang, G., Fratoni, M., Vujic, J. and Greenspan, E. (2015) "Once-Through Thorium Blanket Driven to Very High Burnup by Fast Reactor Excess Neutrons." Trans. Am. Nucl. Soc., 112 (2015) 762-766.
Zhang, Y. and Mikityuk, K. (2016) "Static and transient analysis of a medium-sized sodium cooled fast reactor loaded with oxide, nitride, carbide and metallic fuels." Ann. Nucl. Energy, 87 (2016) 761-771.
Zorla, E., Ipbuker, C., Biland, A., Kiisk, M., Kovaljovc, S., Tkaczyk, A. and Gulik, V. (2017) "Radiation shielding properties of high performance concrete reinforced with basalt fibers infused with natural and enriched boron." Nucl. Eng. Design, 313 (2017) 306-318.
Zweibaum, N., Cao, G., Cisneros, A., Kelleher, B., Laufer, M., Scarlat, R., Seifried, J., Anderson, M. Forsberg, C., Greenspan, E., Hu, L., Peterson, P. and Sridharan, K. (2014) "Phenomenology, methods and experimental program for fluoride-salt-cooled, high-temperature reactors (FHRs)." Prog. Nucl. Energy, 77 (2014) 390-405.

Other references

Becker, B., Dagan, R. and Lohnert, G. (2009) "Proof and implementation of the stochastic formula for ideal gas, energy dependent scattering kernel." Ann. Nucl. Energy, 36 (2009) 470-474.
Cetnar, J. (2006) "General solution of Bateman equations for nuclear transmutations." Ann. Nucl. Energy, 33 (2006) 640-645.
Fridman, E., Shwageraus, E. and Galperin, A. (2008a) "Implementation of multi-group cross-section methodology in BGCORE MC-depletion code." In proc. PHYSOR 2008, Interlaken, Switzerland, Sept. 14-19, 2008.
Fridman, E., Shwageraus, W. and Galperin, A. (2008b) "Efficient generation of one-group cross sections for coupled Monte Carlo depletion calculations." Nucl. Sci. Eng., 159 (2008) 37-47.
Haeck, W. and Verboomen, B. (2007) "An optimum approach to Monte Carlo burnup." Nucl. Sci. Eng., 156 (2007) 180-196.
Hoogenboom, J. E., Martin, W. R. and Petrovic, B. (2010) "Monte Carlo performance benchmark for detailed power density calculation in a full size reactor core." OECD/NEA Data Bank, 2010. (Website)
Horelik, N. and Herman, B. (2012) "Benchmark for evaluation and validation of reactor simulations." MIT Computational Reactor Physics Group, 2012. (Website)
Kelly, D., Sutton, T. and Wilson, S. (2012) "MC21 Analysis of the Nuclear Energy Agency Monte Carlo Performance Benchmark Problem." In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, 2012.
Kiedrowski, B., Brown, F. and Wilson, P. (2011) "Adjoint-weighted tallies for k-eigenvalue calculations with continuous-energy Monte Carlo." Nucl. Sci. Eng., 168 (2011) 226-241.
Koebke, K. (1978) "A new approach to homogenization and group condensation." IAEA-TECDOC-231, International Atomic Energy Agency, 1978.
Mattila, R. (2002) "Three-dimensional analytic function expansion nodal model." YE-PD-9/2002, VTT Technical Research Centre of Finland, 2002.
Ranta-Aho, A., 2007. "Burnup calculations for an EPR-type assembly. Comparison of CASMO-4E and ABURN." In Proc. XIII Meeting on Reactor Physics Calculations in the Nordic Countries. Västerås, Sweden, 29-30 March, 2007.
Smith, K. (1980) "Spatial homogenization methods for light water reactor analysis." Ph.D. Thesis, Massachusetts Institute of Technology, 1980.
Woodcock, E. R., Murphy, T., Hemmings, P. J. and Longworth, T. C. (1965) "Techniques used in the GEM code for Monte Carlo neutronics calculations in reactors and other systems of complex geometry." ANL-7050, Argonne National Laboratory, 1965.