Methods for calculating the release to birth ratio of volatile fission products
Creators
- 1. Shanghai Jiao Tong University, Shanghai (China)
- 2. Shanghai Nuclear Engineering Research and Design Institute, Shanghai (China)
Description
Background: A large quantity of fission products would be produced when the nuclear reactor runs. These fission products would be released to the pellet-rod gap and then to the primary circuit while the fuel rod is broken. The fission products in the primary circuit become the main source term of the reactor. Purpose: This study aims to analysis the source term accurately by calculating the release to birth ratio (RBR) of volatile fission products precisely. Methods: After researching American NRC ANSI/ANS-5.4 methods and French methods for calculating the RBR of volatile fission products, we calculated the RBR of volatile fission products of a fuel rod at different power and different burn-up by these methods, and made some comparison and analysis of these results. Results: Computation results showed that the RBR of volatile fission products would increase with the power and burn-up of the fuel rod. Compared with the ANSI/ANS-5.4-2011, the French method is more conservative whilst the ANSI/ANS-5.4-1982 is the most conservative among these methods. Conclusion: ANSI/ANS-5.4-2011 is the best method among these three methods and it can be used to calculate the release to birth ratio of volatile fission products with good results. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Techniques
- Journal Volume
- 38
- Journal Issue
- 4
- Journal Page Range
- [5 p.]
- ISSN
- 0253-3219
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 49086736
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BURNUP; CALCULATION METHODS; COMPARATIVE EVALUATIONS; COMPUTER CODES; FISSION PRODUCTS; FUEL RODS; PARTURITION; PELLETS; PWR TYPE REACTORS; SOURCE TERMS; VOLATILITY
- Descriptors DEC
- ENRICHED URANIUM REACTORS; EVALUATION; FUEL ELEMENTS; ISOTOPES; MATERIALS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 figs., 8 refs.; http://dx.doi.org/10.11889/j.0253-3219.2015.hjs.38.040605