Published May 2008
| Version v1
Miscellaneous
Preliminary Structural Evaluation of the SMFR Core Support Structure
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
The advanced reactor concepts are needed to meet the waste management, further enhanced safety, nonproliferation, and resource challenges that must accompany the deployment of increasing numbers of nuclear power plants. The SMFR(Small Modular Fast Reactor) was developed jointly by an international collaborative effort to achieve technical consensus. The SMFR has the design features of a pool-type arrangement, sodium coolant, 60 years plant life, 30 years core life, top reactor support and so on. In this study, the preliminary structural integrity for the SMFR core support structure including the inlet plenum and reactor vessel(RV) bottom head is investigated by using the ASME-NG rules for a normal operating condition
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS spring meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2008 spring meeting of the KNS
- Dates
- 29-30 May 2008
- Place
- Kyeongju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 39108984
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DESIGN; EVALUATION; FAST REACTORS; REACTOR CORES; REACTOR OPERATION; REACTOR VESSELS; SAFETY; WASTE MANAGEMENT
- Descriptors DEC
- CONTAINERS; EPITHERMAL REACTORS; MANAGEMENT; OPERATION; REACTOR COMPONENTS; REACTORS
Optional Information
- Notes
- 4 refs, 4 figs, 1 tab