Published October 2014 | Version v1
Miscellaneous Metadata-only

Comparison Study on Thermal-Hydraulic Analysis Depending on Liquid Relief Valve Response for an Station Blackout in CANDU-6

Creators

  • 1. KHNP-CRI, Daejeon (Korea, Republic of)
  • 2. Nuclear Engineering Service and Solution Co., Daejeon (Korea, Republic of)

Description

The purpose of this analysis is to compare the results of thermal-hydraulic analysis depending on liquid relief valve response during a station black out (SBO) events in CANDU-6. The primary heat transport system (PHTS) behavior following the postulated SBO is analyzed using CATHENA code. In the paper, analysis was performed to evaluate the effect on coolant system where LRVs are assumed to be opened or opened according to normal open characteristics in the condition of SBO. The result showed that the primary pressure boundary is extended from LRV to DCT and the effects on primary system behavior were neglectable

Part of:
Proceedings of the KNS 2014 Fall Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2014 Fall Meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2014 Fall Meeting of the KNS
Dates
29-31 Oct 2014
Place
Pyongchang (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
46060863
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CANDU TYPE REACTORS; OUTAGES; RELIEF VALVES; THERMAL HYDRAULICS
Descriptors DEC
CONTROL EQUIPMENT; EQUIPMENT; FLOW REGULATORS; FLUID MECHANICS; HEAVY WATER MODERATED REACTORS; HYDRAULICS; MECHANICS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS; VALVES

Optional Information

Notes
2 refs, 3 figs, 1 tab