Published September 2011 | 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 (Annual safety research report, JFY 2010)

  • 1. Japan Nuclear Energy Safety Organization, Nuclear Energy System Safety Division, Tokyo (Japan)

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 2010, the following results are obtained. As for the development of safety evaluation methods needed in the safety examination achieved for the reactor establishment permission, development of the analysis codes such as core seismic analysis code, core safety analysis code and core damage analysis code were carried out according to the plan. 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, and the seismic PSA to evaluate residual risk was studied. (author)

Part of:
Annual safety research report, JFY 2010

Additional details

Publishing Information

Imprint Title
Annual safety research report, JFY 2010
Imprint Pagination
444 p.
Journal Page Range
p. 145-154
Report number
JNES-RE--2011-0001

Optional Information

Notes
13 figs., 1 tab.; This record replaces 46085135