Published October 2009
| Version v1
Miscellaneous
Core Damage Event Tree Analysis for SFR-600 Level 2 PSA
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
The Korea Atomic Energy Research Institute has been developing Sodium-cooled Fast reactor (SFR) design technologies. Licensing procedures and regulatory requirements are also under establishment for the Gen-IV reactors by the domestic regulatory organization. One of the design requirements of SFR will be to apply the probabilistic safety assessment (PSA) to the design process. Consistent with the design requirements, the PSA would be carried out. On the other hand, there is no experience of the PSA domestically for a fast reactor with the metal fuel. Therefore, the objective of paper is to establish the methodologies of the core damage event tree analysis as a part of Level 2 PSA for the SFR-600 reactor
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2009 autumn meeting of the KNS
- Dates
- 29-30 Oct 2009
- Place
- Kyungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 41027325
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DESIGN; FAILURE MODE ANALYSIS; LICENSING; PROBABILITY; SAFETY ANALYSIS; SODIUM COOLED REACTORS
- Descriptors DEC
- LIQUID METAL COOLED REACTORS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS
Optional Information
- Notes
- 1 ref, 3 figs, 1 tab