Development and Applications of Nuclear Design and Safety Assessment Program SuperMC for Fast Reactoron
- 1. University of Science and Technology of China, Hefei, Anhui, 230027 (China)
- 2. Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China)
Description
Compared with the other reactor types, the neutron spectrum of fast reactors is hard, affecting the neutronics and safety performance, for which advanced nuclear simulation methods such as Monte Carlo method is necessary for the core design. Super Monte Carlo Program for Nuclear and Radiation Simulation (SuperMC) is a general, intelligent, accurate and precise program for the design and safety evaluation of nuclear system including fast reactors. The latest version of SuperMC can accomplish the n, γ transport calculation and depletion calculation, and is integrated with CAD-based automatic modeling, visualization and cloud computing framework. More than 2000 benchmark models and experiments have been duly verified and validated, including the nuclear analyses of fast reactor benchmarks BN600, IAEA-ADS, etc. (author)
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Additional details
Identifiers
Publishing Information
- Imprint Title
- International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Programme and Papers
- Imprint Pagination
- vp.
- Journal Page Range
- 6 p.
- Report number
- IAEA-CN--245
Conference
- Title
- International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development
- Acronym
- FR17
- Dates
- 26-29 Jun 2017
- Place
- Yekaterinburg (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49086041
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BELOYARSK-3 REACTOR; BENCHMARKS; EXPERIMENT RESULTS; FAST REACTORS; IAEA; MONTE CARLO METHOD; NEUTRON SPECTRA; NEUTRON TRANSPORT THEORY; PERFORMANCE; REACTOR DESIGN; RISK ASSESSMENT; SAFETY ANALYSIS; SIMULATION
- Descriptors DEC
- BREEDER REACTORS; CALCULATION METHODS; DESIGN; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; INTERNATIONAL ORGANIZATIONS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; POWER REACTORS; REACTOR LIFE CYCLE; REACTORS; SODIUM COOLED REACTORS; SPECTRA; TRANSPORT THEORY
Optional Information
- Contract/Grant/Project number
- Project XDA03040000; 11305203; 11305205
- Notes
- 16 refs., 3 figs., 1 tab.
- Secondary number(s)
- IAEA-CN--245-346