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Design pressure and design program of shutdown cooling system to prevent the interfacing system LOCA for PWR

Technical Report:

Abstract

This is a technical state of the art report for the prevention methodology of the Interfacing System LOCA (ISLOCA) resulted from the rupture of the Shutdown Cooling System outside the containment which is designed at low pressure and directly connected to the Reactor Coolant System in Pressurized Water Reactor. The ISLOCA had occurred in the U.S.A. (three reported event, Vermont Yankee-12/12/75, Browns Ferry 1-8/14/84, and Pilgrim-9/29/83), and the U.S. NRC reviewed the event in early 1980s. The U.S. NRC`s review results revealed that the probability of ISLOCA is considerably higher than expected. As a result, the U.S. NRC began to have a great concerns for the ISLOCA. The nuclear power plant suppliers in U.S.A. have also tried to improve the system to prevent the ISLOCA. While the U.S. NRC did not express any official position or issue the design requirements for the ISLOCA as of 1992, the nuclear power plant suppliers present the conceptual design features without detail design analysis. The ongoing project of Ulchin Nuclear Power Plant Units 3 and 4 (UCN 3/4) design in Korea requires prevention of the ISLOCA, however, there are some difficulties in implementing the design requirements in the aspects of system configuration and component  More>>
Authors:
Park, Sung Chan; Oh, Jong Phil; Kim, Ho Young [1] 
  1. Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)
Publication Date:
Apr 01, 1993
Product Type:
Technical Report
Report Number:
KAERI/AR-375/93
Reference Number:
SCA: 210200; PA: AIX-25:006626; EDB-94:012335; ERA-19:006602; NTS-94:014832; SN: 94001126507
Resource Relation:
Other Information: PBD: Apr 1993
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; DESIGN; HEAT EXCHANGERS; LOSS OF COOLANT; NUCLEAR POWER PLANTS; PIPES; PUMPS; SHUTDOWN; VALVES; 210200; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED
OSTI ID:
10113020
Research Organizations:
Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
English
Other Identifying Numbers:
Other: ON: DE94610814; TRN: KR9300171006626
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
66 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Park, Sung Chan, Oh, Jong Phil, and Kim, Ho Young. Design pressure and design program of shutdown cooling system to prevent the interfacing system LOCA for PWR. Korea, Republic of: N. p., 1993. Web.
Park, Sung Chan, Oh, Jong Phil, & Kim, Ho Young. Design pressure and design program of shutdown cooling system to prevent the interfacing system LOCA for PWR. Korea, Republic of.
Park, Sung Chan, Oh, Jong Phil, and Kim, Ho Young. 1993. "Design pressure and design program of shutdown cooling system to prevent the interfacing system LOCA for PWR." Korea, Republic of.
@misc{etde_10113020,
title = {Design pressure and design program of shutdown cooling system to prevent the interfacing system LOCA for PWR}
author = {Park, Sung Chan, Oh, Jong Phil, and Kim, Ho Young}
abstractNote = {This is a technical state of the art report for the prevention methodology of the Interfacing System LOCA (ISLOCA) resulted from the rupture of the Shutdown Cooling System outside the containment which is designed at low pressure and directly connected to the Reactor Coolant System in Pressurized Water Reactor. The ISLOCA had occurred in the U.S.A. (three reported event, Vermont Yankee-12/12/75, Browns Ferry 1-8/14/84, and Pilgrim-9/29/83), and the U.S. NRC reviewed the event in early 1980s. The U.S. NRC`s review results revealed that the probability of ISLOCA is considerably higher than expected. As a result, the U.S. NRC began to have a great concerns for the ISLOCA. The nuclear power plant suppliers in U.S.A. have also tried to improve the system to prevent the ISLOCA. While the U.S. NRC did not express any official position or issue the design requirements for the ISLOCA as of 1992, the nuclear power plant suppliers present the conceptual design features without detail design analysis. The ongoing project of Ulchin Nuclear Power Plant Units 3 and 4 (UCN 3/4) design in Korea requires prevention of the ISLOCA, however, there are some difficulties in implementing the design requirements in the aspects of system configuration and component manufacturing. This report summurized the current position of the U.S. NRC and the design concept of the Advanced Light Water Reactor. Based on these review, design features which can prevent the ISLOCA are presented for use in the UCN 3/4 or future plant design. (Author).}
place = {Korea, Republic of}
year = {1993}
month = {Apr}
}