Published October 2018 | Version v1
Miscellaneous

Safety Analysis of ATWS Events for PGSFR

  • 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.

Part of:
Proceedings of the KNS 2018 Fall Meeting

Additional details

Identifiers

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