EPJ Web Conf.
Volume 247, 2021PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
|Number of page(s)||8|
|Section||Core Analysis Methods|
|Published online||22 February 2021|
- Lee H et al., “MCS – A Monte Carlo Particle Transport Code for Large-scale Power Reactor Analysis,” Annuals of Nuclear Energy (2019). (Under review) [Google Scholar]
- Leppänen J et al., “The Serpent Monte Carlo Code: Status, Development and Applications in 2013,” Annals of Nuclear Energy, 82, 142-150 (2015). [Google Scholar]
- Choe J et al., “Verification and validation of STREAM/RAST-K for PWR analysis,” Nuclear Engineering and Technology, 51(2), 356-368 (2019). [Google Scholar]
- Downar T, “PARCS v2.7 U.S. NRC Core Neutronics Simulator USER MANUAL,” U.S. NRC (2006). [Google Scholar]
- Hoogenboom J et al., “Generation of Multi-group Cross Sections and Scattering Matrices with the Monte Carlo Code MCNP5,” Proc. Joint International Topical Meeting on Mathematics & Computation and Supercomputing in Nuclear Applications, Monterey, California, April 15-19, p.15-19 (2007). [Google Scholar]
- Bernnat W et al., “Benchmark for Neutronic Analysis of Sodium-Cooled Fast Reactor Cores with Various Fuel Types and Core Sizes,” Nuclear Energy Agency Technical Report, NEA/NSC (2015). [Google Scholar]
- Pereira G et al., “Applying the Serpent-DYN3D Code Sequence for the Decay Heat Analysis of Metallic Fuel Sodium Fast Reactor,” Annals of Nuclear Energy, 125, 291-306 (2019). [Google Scholar]
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