Safety Analysis for Sub-channel Blockage in the PGSFR
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
The flow perturbation caused by the blockage could raise the local coolant temperature in the incident and it might eventually lead to the degradation of the fuel rods. Therefore, a partial flow blockage accident must be a safety concern in the SFR design. In this regard, analyses were performed for the flow blockage accident postulated in a conceptual design of a 150MWe Proto-type SFR using the MATRA-LMR/FB and analysis result was compared to the safety acceptance criterion shown in Table 1 developed by KAERI. The maximum coolant temperatures for 6, 24 channels blockage occurred at the end of the fuel slug and both of them satisfied the safety limits. However, for the 54 channels blockage, the maximum coolant temperature was found in the downstream of the blockage and it could not meet the safety limits. It was caused by the recirculation region in the downstream of the blockage. In conclusion, satisfactory margins were obtained for 6, 24 channel blockage cases
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2014 spring meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2014 spring meeting of the KNS
- Dates
- 28-30 May 2014
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 46050501
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DAMAGE; DESIGN; FLOW BLOCKAGE; FUEL ASSEMBLIES; PERTURBATION THEORY; SAFETY; SAFETY ANALYSIS; SODIUM COOLED REACTORS
- Descriptors DEC
- LIQUID METAL COOLED REACTORS; REACTORS
Optional Information
- Notes
- 4 refs, 5 figs, 1 tab