Source: http://montecarlo.vtt.fi/publications.htm
Timestamp: 2019-04-21 02:11:48+00:00

Document:
• 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.
• 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. (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. (2019) "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.
• 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. 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. 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. 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.
• 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. 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.
• 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.
• 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).
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