Published May 2015
| Version v1
Miscellaneous
2014 PGSFR Safety Analysis for Loss of Flow
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
The PGSFR consists of the PHTS (Primary Heat Transport System), the IHTS (Intermediate Heat Transport System), and the DHRS (Decay Heat Removal System). A LOF (Loss Of Flow) accident has been investigated for a safety evaluation of the PGSFR using the MARSLMR code. The safety analysis is evaluated by a CDF (Cumulative Damage Fraction). In case of the LOF accident, the tentative safety criterion is the CDF of under 0.05. The LOF accident has been evaluated in the PGSFR using MARS-LMR. The accident was initiated by both of PHTS pump trip. In the results, the CDF was predicted below a tentative safety criterion of 0.05 with a sufficient margin. The DHRS acceptably functioned for removing the core decay heat during long-term cooling period
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2015 spring meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2015 spring meeting of the KNS
- Dates
- 6-8 May 2015
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 47022991
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT REMOVAL; COOLING; DAMAGE; HEAT TRANSFER; LOSS OF FLOW; M CODES; PUMPS; SAFETY ANALYSIS; SODIUM COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; EQUIPMENT; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTORS; REMOVAL
Optional Information
- Notes
- 1 ref, 5 figs