A preliminary research to develop the DNBR limit using a sampled statistics method
Creators
- 1. Shanghai Nuclear Engineering Research and Design Institute Co., Ltd., Shanghai (China)
Description
The departure from nucleate boiling (DNB) design basis is one of the important reactor core thermal-hydraulic design bases. To avoid the DNB phenomenon, the departure from nucleate boiling ratio (DNBR) design limit corresponding to a certain confidence level should be developed. Thus, a research using a sampled statistics method was conducted to develop the DNBR limit. A reasonable design flow was proposed in this paper, the parameters to be sampled included almost all parameters influencing the DNBR, for example, the power distribution, model uncertainties, state parameters. A coupled code was developed to execute the sampled job and to carry out the DNBR calculation. Meanwhile, the typical LOFA was selected to evaluate the DNBR margin. The results showed that the sampled statistics methodology described in this paper has practical applications. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 27th international conference on nuclear engineering (ICONE-27)
- Imprint Pagination
- [4028 p.]
- Journal Page Range
- 5 p.
Conference
- Title
- 27. international conference on nuclear engineering
- Acronym
- ICONE-27
- Dates
- 19-24 May 2019
- Place
- Tsukuba, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 51012955
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTER CODES; CORRELATIONS; CRITICAL HEAT FLUX; DEPARTURE NUCLEATE BOILING; DESIGN-BASIS ACCIDENTS; HYPOTHETICAL ACCIDENTS; LOSS OF FLOW; NUCLEAR POWER PLANTS; POWER DISTRIBUTION; PROBABILITY DENSITY FUNCTIONS; REACTOR CORES; REACTOR OPERATION; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; BOILING; FLUID MECHANICS; FUNCTIONS; HEAT FLUX; HYDRAULICS; MECHANICS; NUCLEAR FACILITIES; NUCLEATE BOILING; OPERATION; PHASE TRANSFORMATIONS; POWER PLANTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR LIFE CYCLE; THERMAL POWER PLANTS
Optional Information
- Notes
- Available as Internet Data in PDF format, Folder Name: Track08, Paper ID: ICONE27-1831F.pdf; 2 refs., 3 figs., 3 tabs.