Published October 2018
| Version v1
Miscellaneous
Safety Analysis of ATWS Events for PGSFR
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
- 2. Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)
Description
The PGSFR (Prototype Gen-Ⅳ Sodium-cooled Fast Reactor) consists of the PHTS (Primary Heat Transport System), the IHTS (Intermediate Heat Transport System), and the DHRS (Decay Heat Removal System). Four events of Unprotected Transient Over-Power (UTOP), Unprotected Loss OF Flow (ULOF), Unprotected Loss Of Heat Sink (ULOHS), and Unprotected Station Black-Out (USBO) are selected as representative events for the Anticipated Transient Without Scram (ATWS). Safety analysis of four representative ATWS events are carried out with MARS-LMR code. Safety analysis of four representative ATWS events has been implemented using MARS-LMR code. As a results, the peak assembly outlet temperatures fulfill the safety acceptance criteria.
Additional details
Identifiers
- URL
- https://www.kns.org;
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2018 Fall Meeting
- Imprint Pagination
- vp.
- Journal Page Range
- [3 p.]
Conference
- Title
- 2018 Fall Meeting of the KNS
- Dates
- 24-26 Oct 2018
- Place
- Yeosu (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 50060159
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT REMOVAL; ATWS; HEAT TRANSFER; KAERI; M CODES; REACTIVITY; SAFETY ANALYSIS; SODIUM COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; KOREAN ORGANIZATIONS; LIQUID METAL COOLED REACTORS; NATIONAL ORGANIZATIONS; REACTOR ACCIDENTS; REACTORS; REMOVAL
Optional Information
- Notes
- 3 refs, 5 figs