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.
Aufiero, M., Bidaud, A., Kotlyar, D., Leppänen, J., Palmiotti G., Salvatores, M., Sen S., Shwageraus, E. and Fratoni, M. (2017a) "New Approaches and Applications for Monte Carlo Perturbation Theory." In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
Aufiero, M., Fratoni, M., Palmiotti, G. and Salvatores, M. (2017b) "Continuous Energy Cross Section Adjustment: a New Method to Generalize Nuclear Data Assimilation for a Wider Range of Applications." In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
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.
Kaltiaisenaho, T. (2019) "Photonuclear Reactions in Serpent 2 Monte Carlo Code." In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
Kaltiaisenaho, T. (2020) "Photon transport physics in Serpent 2 Monte Carlo code." Comp. Phys. Comm., 252 (2020) 107143.
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.
Leppänen, J. (2017a) "On the use of delta-tracking and the collision flux estimator in the Serpent 2 Monte Carlo particle transport code." Ann. Nucl. Energy, 105 (2017) 161-167.
Leppänen, J., Kaltiaisenaho, T., Valtavirta, V. and Metsälä, M. (2017b) "Development of a Coupled Neutron / Photon Transport Mode in the Serpent 2 Monte Carlo Code." In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
Leppänen, J., Viitanen, T. and Hyvönen, O. (2017c) "Development of a Variance Reduction Scheme in the Serpent 2 Monte Carlo Code." In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
Leppänen, J. (2019a) "Response Matrix Method–Based Importance Solver and Variance Reduction Scheme in the Serpent 2 Monte Carlo Code." Nucl. Technol., 205 (2019) 1416-1432.
Leppänen, J. (2019b) "Acceleration of Fission Source Convergence in the Serpent 2 Monte Carlo Code Using a Response Matrix Based Solution for the Initial Source Distribution." Ann. Nucl. Energy, 128 (2019) 63-68.
Leppänen, J. and Jokipii, M. (2019c) "Global Variance Reduction Scheme with Self-Adaptive Weight-Window Mesh in the Serpent 2 Monte Carlo Code." In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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.
Pusa, M. (2016) "Higher-Order Chebyshev Rational Approximation Method and Application to Burnup Equations." Nucl. Sci. Eng., 182 (2017) 297-318.
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.
Sirén, P., Varje, J., Äkäslompolo, S., Asunta, O., Giroud, C., Kurki-Suonio, T. and Weisen, H. (2017) "Versatile fusion source integrator AFSI for fast ion and neutron studies in fusion devices." Nucl. Fusion, 58 (2017) 016023.
Sirén, P., Varje, Weisen, H. and Koskela, T. (2017) "Synthetic neutron camera and spectrometer in JET based on AFSI-ASCOT simulations." J. Instrum., 12 (2017) C09010.
Sirén, P. (2018) "Modelling of JET and ITER reactor relevant plasma neutron source for neutronics calculation chain." D.Sc. Thesis, Aalto University, 2018.
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.
Tuominen, R., Valtavirta, V. and Leppänen, J. (2018) "Application of the Serpent–OpenFOAM Coupled Code System to the SEALER Reactor Core." In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
Tuominen, R., Valtavirta, V. and Leppänen, J. (2019) "New energy deposition treatment in the Serpent 2 Monte Carlo transport code." Ann. Nucl. Energy, 129 (2019) 224-232.
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. (2017a) "Coupled neutronics–fuel behavior calculations in steady state using the Serpent 2 Monte Carlo code." Ann. Nucl. Energy, 100 (2017) 50-64.
Valtavirta, V. and Leppänen, J. (2017b) "Estimating the effects of homogenized fuel temperature in group constant generation using Serpent 2." Ann. Nucl. Energy, 105 (2017) 79-94.
Valtavirta, V. and Leppänen, J. (2017c) "Coupled Burnup Calculations with the Serpent 2 Monte Carlo Code." In proc. M&C 2017, Jeju, Korea, Apr. 16-20, 2017.
Valtavirta, V. (2017d) "Development and applications of multi-physics capabilities in a continuous energy Monte Carlo neutron transport code." D.Sc. Thesis, Aalto University, 2017. (VTT Science 150)
Valtavirta, V. and Leppänen, J. (2018a) "Effects of Fuel Temperature History Approximations on Neutronics Properties of a BWR Assembly." In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
Valtavirta, V. and Leppänen, J. (2018b) "New Stochastic Substep Based Burnup Scheme for Serpent 2." In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
Valtavirta, V., Hovi, V., Loukusa, H., Rintala, A., Sahlberg, V., Tuominen, R. and Leppänen, J. (2019) "Kraken—An Upcoming Finnish Reactor Analysis Framework." In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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." EPJ Web of Conferences, 106 (2016) 03010.
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. (2016a) "New Interpolation Capabilities for Thermal Scattering Data in Serpent 2." In proc. PHYSOR 2016, Sun Valley, ID, May 1-6, 2016.
Viitanen, T. and Leppänen, J. (2016b) "Calculating Neutron Dosimeter Activation in VVER-440 Surveillance Chains with Serpent." In proc. 26th AER Symposium on VVER Reactor Physics and reactor safety, Helsinki, Finland, Oct. 10-14, 2016.
Wendt, B., Kerby, L., Tumulak, A., Leppänen, J. and DeHart, M. (2017) "Advancement of Functional Expansion Tallies Capabilities in Serpent 2." Trans. Am. Nucl. Soc., 116 (2017) 552-555.

Theses and student projects with Serpent applications

Ahimsa, M. (2017) "Design Analysis of Fuel Assembly and Reactor Core of Floating Nuclear Power Plant KLT-40S using SERPENT." B.Sc. Thesis, Universitas Gadjah Mada, 2017.
Alam, S. (2018) "The Design of Reactor Cores for Civil Nuclear Marine Propulsion." Ph.D. Thesis, University of Cambridge, 2018.
Alameri, S. (2015) "A coupled nuclear reactor thermal energy storage system for enhanced load following operation." Ph.D. Thesis, Colorado School of Mines, 2015.
Alberti, A. "Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility." M.Sc. Thesis, Oregon State University, 2016.
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).
Bae, J. (2018) "Fuel cycle transition simulation capabilities in CYCLUS." M.Sc. Thesis, University of Illinois, 2018.
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.
Bao, J. (2016) "Development of the model for the multiphysics analysis of Molten Salt Reactor Experiment using GeN-Foam code." M.Sc. Thesis, École Polytechnique Fédérale de Lausanne / Eidgenössische Technische Hochschule Zürich, 2016.
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.
Bartel, J. (2019) "Analysis and Improvement of the bRAPID Algorithm and its Implementation." M.Sc. Thesis, Virginia Tech, 2019.
Beltjens, E. (2017) "Modelling of the low-void SFR core during ULOF with spatial kinetics." M.Sc. Thesis, École Polytechnique Fédérale de Lausanne / Eidgenössische Technische Hochschule Zürich, 2017.
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.
Bianchini, P. (2017) "Computational features of neutronics and thermal hydraulics coupled simulations." M.Sc. Thesis, Politecnico di Milano, 2017.
Blanco, J. (2016) "Triga Reactor calculations using Serpent 2." Dipl. Eng. Thesis, Balseiro Institute, 2016 (in Spanish).
Borowiec, K. (2016) "Investigation of temperature reactivity coefficient in EOLE reactor." B.Sc. Thesis, Warsaw University of Technology, 2016.
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.
Carbol, S. (2017) "Development of a hybrid neutron transport method in 2 energy groups." M.Sc. Thesis, Chalmers University of Technology, 2017.
Castagna, C. (2014) "Modellizzazione al simulatore delle condizioni di criticità 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.
Cywinski, J. (2016) "Study of the re-criticality potential during the ex-vessel phase of severe accident in a Boiling Water Reactor." M.Sc. Thesis, Warsaw University of Technology, 2017.
Descotes, M. (2011) "Reactor Physics of a Deep-burner Prismatic Core for VHTR." M.Sc. Thesis, École Polytechnique de Montréal, 2011.
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.
Demers, Z. (2017) "Comparative Safety Evaluation of Thorium Fuel to Natural Uranium Fuel in a CANDU 6 Reactor." M.Sc. Thesis, McMaster University, 2017.
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 Politècnica 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).
Eriksson, M. (2013) "Förutsättningarna för ett parallellt generation IV system vid svensk nybyggnation av kärnkraft. The prospects for a parallel generation IV reactor in the swedish nuclear system." B.Sc. Thesis, Uppsala University, 2013 (in Swedish).
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.
Giudicelli, G. (2017) "Achievable power uprates in pressurized water reactors using uranium nitride fuel." M.Sc. Thesis, Massachusetts Institute of Technology, 2017.
Gorman, P. (2016) "Design and Analysis of Thorium-fueled Reduced Moderation Boiling Water Reactors." Ph.D. Thesis, University of California, Berkeley, 2016.
Gottfridsson, F. (2010) "Simulation of Reactor Transient and Design Criteria of Sodium-cooled Fast Reactors Simulation of Reactor Transient and Design Criteria of Sodium-cooled Fast Reactors." B.Sc. Thesis, Uppsala University, 2010.
Grodzki, M. (2017) "Neutronic analysis of battery - type high temperature gas-cooled reactor." M.Sc. Thesis, Warsaw University of Technology, 2017.
Guglielmelli, A. (2015) "Calcoli di sezioni d'urto efficaci di riflettore in sistemi PWR di terza generazione." Ph.D. Thesis, University of Bologna, 2015 (in Italian).
Hakim, A. (2017) "Fuel Assembly Design of Small PWR with Uranium Mononitride Fully Ceramic Microencapsulated Fuel using SCALE and SERPENT." B.Sc. Thesis, Universitas Gadjah Mada, 2017.
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.
Harrisson, G. (2015) "Calculation of a Canadian SCWR fuel channel taking into account the conditions of the materials and the axial coupling." Ph.D. Thesis, École Polytechnique de Montréal, 2015.
Hassan, S. (2011) "Spatial dependence of reactivity coefficients." M.Sc. Thesis, Royal Institute of Technology, 2011.
Helgesson, P. (2013) "UO-2 vs MOX: Propagated nuclear data uncertainty with burnup using Fast Total Monte Carlo." B.Sc. Thesis, Uppsala University, 2013.
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.
Hiscox, B. (2018) "Analysis and Optimization of a New Accident Tolerant Fuel Called Fuel-in-Fibers." M.Sc. Thesis, Massachusetts Institute of Technology, 2018.
Hombourger, B. (2018) "Conceptual Design of a Sustainable Waste Burning Molten Salt Reactor." Ph.D. Thesis, École Polytechnique Fédérale de Lausanne / Eidgenössische Technische Hochschule Zürich, 2018.
Hrabar, Y. (2019) "Development, benchmarking and validation of the Advanced Nuclear Fuel Cycle Simulator FANCSEE and advanced use of Monte Carlo methods in nuclear reactor calculations." M.Sc. Thesis, University Paris-Saclay, 2019.
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.
Hyvönen, O. (2019) "Variance reduction methods in Monte Carlo particle transport simulations." Special assignment, Aalto University, 2019.
Ignaczak, P. (2016) "Monte Carlo Simulation of the AP1000 Nuclear Reactor." M.Sc. Thesis, Warsaw University of Technology, 2017.
Inkinen, P. (2009) "Implementation of nodal diffusion model into APROS." M.Sc. Thesis, Helsinki University of Technology, 2009.
Ivanov, A. (2015) "High Fidelity Monte Carlo Based Reactor Physics Calculations." Dr.-Ing. Thesis, Karlsruhe Institute of Technology, 2015.
Jo, Y., Kong, C., Cherezov, A., Lee, D. (2019) "Sensitivity and Uncertainty Analysis Capability in MCS for UAM Benchmark." In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
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)
Kaartinen, D. (2019) "Laskentakoodien Vertailu Säteilymittarien Sijoitus- ja Suoritusanalyysissä." M.Sc. Thesis, Lappeenranta University of Technology, 2019 (in Finnish).
Kalinainen, T. (2016) "Modelling of Decay Heat with Exponential Functions in Serpent 2." Special assignment, Aalto University, 2016.
Karlsson, D. and Kollberg, E. (2015) "Säkerhetsegenskaper hos en rymdreakto." B.Sc. Thesis, Royal Institute of Technology, 2015 (in Swedish).
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.
Knebel, M. (2017) "Advanced high-fidelity reactor simulators based on neutron transport and subchannel methodologies." Dr.-Ing. Thesis, Karlsruhe Institute of Technology, 2017.
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.
Kubinski, W. (2017) "Neutronic analysis of a liquid sodium cooled fast nuclear reactor core using a Monte Carlo method.", B.Sc. Thesis, Warsaw University of Technology, 2017 (in Polish).
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.
Lago, D. (2017) "Development of an application programming interface for depletion analysis (APIDA)." Ph.D. Thesis, Georgia Institute of Technology, 2017.
Laureau, A. (2015) "Développement de modèles neutroniques pour le couplage thermohydraulique du MSFR et le calcul de paramètres 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.
Le Meur, L. (2018) "Etude des propriétés de désintégration bêta de noyaux exotiques d'intérêts pour la physique des réacteurs, la structure nucléaire et l'astrophysique nucléaire, à l'aide de la technique de Spectroscopie Gamma par Absorption Totale (TAGS)." Ph.D. Thesis, University of Nantes, 2018.
Lovecký, M. (2017) "Increasing the effciency of nuclear fuel using burnable absorbers." D.Sc. Thesis, University of West Bohemia, 2017.
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).
Mardus-Hall, R., Ho, M., Pastrello, A. and Yeoh, G. (2020) "3-Way coupled thermohydraulic-discrete element-neutronic simulation of solid fuel, molten salt reactor." Ann. Nucl. Energy, 135 (2020) 106973.
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.
Mehta, V. (2018) "Spectral Shift Operated SMAHTR to Improve Cycle Length and Discharge Burnup Continuously." M.Sc. Thesis, Georgia Institute of Technology, 2018.
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.
Mikolajczak, A. (2016) "Neutronic analysis of Sodium-cooled Fast Reactor ores with Various Fuel Types." M.Sc. Thesis, Warsaw University of Technology, 2017.
Moberg, K. (2012) "An investigation of fuel cycles and material flows for a lead-cooled fast reactor using the Monte Carlo code Serpent." B.Sc. Thesis, Uppsala University, 2012.
Muszynski, D. (2017) "Testing accuracy of rectangular diffusion model of Maria reactor." M.Sc. Thesis, Warsaw University of Technology, 2017.
Nikitin, E. (2019) "Extension of the nodal code DYN3D to SFR applications ." Ph.D. Thesis, École Polytechnique Fédérale de Lausanne, 2018.
Obrebski, P. (2017) "The Beginning of Cycle Monte Carlo 3 D Simulations of the AP1000 Core." M.Sc. Thesis, Warsaw University of Technology, 2017.
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.
Pereira, G. (2018) "Applying a nodal diffusion-micro depletion sequence for high-fidelity analysis of sodium cooled fast reactors." M.Sc. Thesis, Georgia Institute of Technology, 2018.
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.
Potapczyk, K. (2016) "Potential Re-Criticality of BWR Core During Re- Flooding Phase of Sever Accident." M.Sc. Thesis, Warsaw University of Technology, 2017.
Preciado, M. (2014) "Development of a KONVOI PWR Core Model for Coupled TRACE/PARCS Simulations." B.Sc. Thesis, Universitat Polytecnica de Valencia, 2014.
Quinteros, F. (2016) "RA-10 reactor modelling using Serpent code." Dipl. Eng. Thesis, Balseiro Institute, 2016 (in Spanish).
Qvist, S. (2013) "Core design and safety of large liquid metal cooled fast breeder reactors." Ph.D. Thesis, University of California Berkeley, 2013.
Rais, A. (2018) "Performance assessment of a 3-D steady-state and spatial kinetics model for the CROCUS reactor." Ph.D. Thesis, École Polytechnique Fédérale de Lausanne / Eidgenössische Technische Hochschule Zürich, 2018.
Ramey, K. (2017) "Development of serpent-based methods for I2S-LWR depletion modeling and sensitivity studies." M.Sc. Thesis, Georgia Institute of Technology, 2017.
Raouafi, Haykel (2017) "Simulation de mécanismes de contrôle de la réactivité inclinés du réacteur SCWR-canadien en utilisant les codes DRAGON-5 et DONJON-3." M.Sc. Thesis, École Polytechnique de Montréal, 2017 (in French).
Raub, S. (2011) "Transient behaviour in a BWR with Hafnium Cladding." M.Sc. Thesis, Royal Institute of Technology, 2011.
Rawlins, S. (2018) "Feasibility and Parameterization of Small-scale Low-Enriched Uranium Nuclear Thermal Propulsion." M.Sc. Thesis, Korea Advanced Institute of Science and Technology, 2018.
Reiter, C. (2019) "A model system for transient calculations for research reactors with a compact core." Ph.D. Thesis, Technische Universität München, 2019.
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).
Rykhlevskii, A. (2018) "Advanced online fuel reprocessing simulation for thorium-fueled molten salt breeder reactor." M.Sc. Thesis, University of Illinois, 2018.
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. (2016a) "Modelling of axial discontinuities in reactor cores with Serpent 2 - TRAB3D code sequence." M.Sc. Thesis, Aalto University, 2016.
Sallinen, I. (2017) "Sensitivity testing of the fusion neutron calculation chain consisting of ASCOT and AFSI." B.Sc. Thesis, Aalto University, 2017.
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.
Salah, S. (2011) "Spatial dependence of reactivity coefficients." B.Sc. Thesis, Royal Institute of Technology, 2011.
Sartori, A. (2015) "Reduced order methods: applications to nuclear reactor core spatial dynamics." Ph.D. Thesis, Politecnico di Milano, 2015.
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.
Skwarcan-Bidakowski, A. (2017) "Nuclear reactor core model for the advanced nuclear fuel cycle simulator FANCSEE. Advanced use of Monte Carlo methods in nuclear reactor calculations." B.Sc. Thesis, Uppsala University, 2017.
Sukjai, Y. (2018) "Fuel performance modeling of high burnup mixed oxide fuel for hard spectrum LWRs." Ph.D. Thesis, Massachusetts Institute of Technology, 2018.
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.
Svanström, S. (2016) "Load following with a passive reactor core using the SPARC design." B.Sc. Thesis, Uppsala University, 2016.
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.
Vitullo, F. (2017) "Statistical burnup distribution of moving pebbles in HTR-PM reactor." M.Sc. Thesis, École Polytechnique Fédérale de Lausanne / Eidgenössische Technische Hochschule Zürich, 2017.
Westlund, M. (2019) "Monte Carlo Simulations of Bowing Effects Using Realistic Fuel Data in Nuclear Fuel Assemblies." M.Sc. Thesis, Uppsala University, 2019.
Wendt, B. (2018) "Functional Expansions Methods: Optimizations, Characterizations, and Multiphysics Practices." Ph.D. Thesis, Idaho State University, 2018.
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.
Wrobel, J. (2016) "Monte Carlo simulations of the EPR nuclear reactor." M.Sc. Thesis, Warsaw University of Technology, 2017.
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.
Yi, H., Demaziere, C., Vinai, P. and Leppänen, J. (2019) "Development and Test of a Hybrid Probabilistic-Deterministic Framework Based on the Interface Current Method." In proc. M&C 2019, Portland, OR, Aug. 25-29, 2019.
Younker, I. (2015) "Neutronic and Economic Evaluation of Accident Tolerant Fuel Concepts for Light Water Reactors." M.Sc. Thesis, Pennsylvania State University, 2015.
Younan, S. (2017) "Comparative study of accident-tolerant fuel for a CANDU lattice." M.Sc. Thesis, McMaster University, 2017.
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.
Zebryk, A. (2016) "Neutronic Analysis of the subcritical reactor MYRRHA with a Code SERPENT." B.Sc. Thesis, Warsaw University of Technology, 2017 (in Polish).
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

Abdelhameed, A., Nguyen, X., Lee, J. and Kim, Y. (2018) "Feasibility of passive autonomous frequency control operation in a Soluble-Boron-Free small PWR." Ann. Nucl. Energy, 116 (2018) 319-333.
Abdo, M., Elzohery, R. and Roberts, J. (2018) "Data-Driven Surrogate Model to Predict Isotopic Composition Using Dynamic Mode Decomposition." In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
Abrate, N., Dulla, S., Ravetto, P. and Bruna, G. (2018) "Assessment of Numerical Methods for the Evaluation of Higher-order Harmonics in Diffusion Theory." In proc. PHYSOR 2018, Cancún, México, Apr. 22-26, 2018.
Abrate, N., Bruna, G., Dulla, S. and Ravetto, P. (2019) "Assessment of numerical methods for the evaluation of higher-order harmonics in diffusion theory." Ann. Nucl. Energy, 128 (2019) 455-470.
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.
Alam, S., Kumar, D., Almutairi, B., Bhowmik, P., Goodwin, C. and Parks, G. (2019) "Small modular reactor core design for civil marine propulsion using micro-heterogeneous duplex fuel. Part I: Assembly-level analysis." Nucl. Eng. Design, 346 (2019) 157-175.
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.
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