Published August 2013
| Version v1
Report
Development of safety evaluation methods and analysis codes applied to the safety regulations for the design and construction stage of fast breeder reactor
Description
The purposes of this study are to develop the safety evaluation methods and analysis codes needed in the design and construction stage of fast breeder reactor (FBR). In JFY 2012, the following results are obtained. As for the development of safety evaluation methods needed in the safety examination conducted for the reactor establishment permission, development of the analysis codes, such as core damage analysis code, were carried out following the planned schedule. As for the development of the safety evaluation method needed for the risk informed safety regulation, the quantification technique of the event tree using the Continuous Markov chain Monte Carlo method (CMMC method) were studied. (author)
Additional details
Publishing Information
- Imprint Title
- Annual safety research report, JFY 2012
- Imprint Pagination
- 708 p.
- Journal Page Range
- p. 171-180
- Report number
- JNES-RE--2013-0001-Rev.1
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 51066938
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- ACCIDENT MANAGEMENT; DAMAGE; FAILURE MODE ANALYSIS; FBR TYPE REACTORS; LOSS OF FLOW; MARKOV PROCESS; MONTE CARLO METHOD; PROBABILISTIC ESTIMATION; REACTOR CORES; REACTOR SAFETY; RISK ASSESSMENT; SAFETY ANALYSIS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; CALCULATION METHODS; EPITHERMAL REACTORS; FAST REACTORS; MANAGEMENT; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; STOCHASTIC PROCESSES; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS
Optional Information
- Notes
- 17 figs., 1 tab.; This record replaces 46032163