Validation of SuperMC based on VENUS-II benchmark experiment
- 1. University of Science and Technology of China, Hefei (China)
- 2. Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei (China)
Description
Super Monte Carlo Program for Nuclear and Radiation Simulation (SuperMC), a general, intelligent, accurate and precise simulation software system for the design and safety evaluation of nuclear systems, is developed by FDS team of key laboratory of neutronics and radiation safety. In order to validate the accuracy of SuperMC in calculating MOX-fueled system, it was benchmarked with the VENUS-II MOX-fueled core model released by OECD/NEA. Both cell and core calculations were performed. A series of key parameters of cell infinite multiplication factor, reaction rates per heavy isotope, core effective multiplication factor, and axial fission rate distribution of six fuel pins were calculated. The computational results are compared with measured data and the MCNP calculated results, showing that the SuperMC results agree well with the experimental results and the MCNP calculated results. The correctness and reliability of SuperMC calculating neutron transport in MOX-fuelled system are preliminarily verified. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- High Power Laser and Particle Beams
- Journal Volume
- 30
- Journal Issue
- 1
- Journal Page Range
- [6 p.]
- ISSN
- 1001-4322
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 55052757
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Descriptors DEI
- ACCURACY; BENCHMARKS; COMPARATIVE EVALUATIONS; DISTRIBUTION; FISSION; FUEL PINS; FUEL SYSTEMS; ISOTOPES; MIXED OXIDE FUELS; MONTE CARLO METHOD; MULTIPLICATION FACTORS; NEUTRON TRANSPORT; RADIATION PROTECTION; REACTION KINETICS; RELIABILITY; S CODES; SAFETY ANALYSIS; SIMULATION; VALIDATION; VENUS PLANET
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; DIMENSIONLESS NUMBERS; ENERGY SOURCES; EVALUATION; FUEL ELEMENTS; FUELS; KINETICS; MATERIALS; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR FUELS; NUCLEAR REACTIONS; PLANETS; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTOR MATERIALS; SOLID FUELS; TESTING
Optional Information
- Notes
- 8 figs., 2 tabs., 12 refs.; http://dx.doi.org/10.11884/HPLPB201830.170218