Application of similarity analysis method in zero-power experimental validation
Creators
- 1. China Institute of Atomic Energy, P. O. Box 275-45, Beijing 102413 (China)
Description
New advanced reactors require zero-power experiments to validate the correctness of design. In order to ensure sufficient validation strength, certain similarity of physical properties between zero-power experimental reactor and the target reactor is required. Based on sensitivity and uncertainty analysis techniques, three indexes for evaluating the physical similarity between reactor systems were introduced. Based on the Monte Carlo transport program MONK, a coupled similarity analysis program MCS was compiled. The results of MCS were compared with TSUNAMI's and the two programs showed good agreement. Finally, the similarity between the CEFR in MOX fuel loading design and the BFS-119-2 zero-power experiment scheme given by IPPE was calculated by MCS. The results showed that the two systems were very similar to each other, and the physical properties of the CEFR-MOX loading design could be validate by the zero-power experiment. Key words: similarity analysis / zero-power experiment / validation
Availability note (English)
Available from https://www.epj-conferences.org/articles/epjconf/pdf/2020/15/epjconf_nd2019_17017.pdf; https://doaj.org/article/4d06023f97d84262903c0ce39399d881Additional details
Identifiers
Publishing Information
- Journal Title
- EPJ. Web of Conferences
- Journal Volume
- 239
- Journal Page Range
- vp.
- ISSN
- 2100-014X
Conference
- Title
- International Conference on Nuclear Data for Science and Technology
- Acronym
- ND 2019
- Dates
- 19-24 May 2019
- Place
- Beijing (China)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 53093333
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPARATIVE EVALUATIONS; EXPERIMENTAL REACTORS; MIXED OXIDE FUELS; MONTE CARLO METHOD; PHYSICAL PROPERTIES; REACTOR DESIGN; SENSITIVITY
- Descriptors DEC
- CALCULATION METHODS; DESIGN; ENERGY SOURCES; EVALUATION; FUELS; MATERIALS; NUCLEAR FUELS; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SOLID FUELS