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Modification of reference temperature program in reactor regulating system

Abstract

In Yonggwang nuclear units 3 and 4 currently under commercial operation, the cold temperature was very close to the technical specification limit of 298 deg C during initial startup testing, which was caused by the higher-than-expected reactor coolant system flow. Accordingly, the reference temperature (Tref) program needed to be revised to allow more flexibility for plant operations. In this study, the method of a specific test performed at Yonggwang nuclear unit 4 to revise the Tref program was described and the test results were discussed. In addition, the modified Tref program was evaluated on its potential impacts on system performance and safety. The methods of changing the Tref program and the associated pressurizer level setpoint program were also explained. Finally, for Ulchin nuclear unit 3 and 4 currently under initial startup testing, the effects of reactor coolant system flow rate on the coolant temperature were evaluated from the thermal hydraulic standpoint and an optimum Tref program was recommended. 6 refs., 4 figs., 2 tabs. (Author)
Authors:
Yu, Sung Sik; Lee, Byung Jin; Kim, Se Chang; Cheong, Jong Sik; [1]  Kim, Ji In; Doo, Jin Yong [2] 
  1. Korea Power Engineering Company, Inc., Seoul (Korea, Republic of)
  2. Korea Electric Power Cooperation, Yonggwang (Korea, Republic of)
Publication Date:
Dec 31, 1998
Product Type:
Conference
Report Number:
ETDE/KR-99732629; CONF-9805154-
Reference Number:
SCA: 210200; 220400; 220900; PA: KR-99:000346; EDB-99:035052; SN: 99002059973
Resource Relation:
Conference: The Korean Nuclear Society spring meeting, Seoul (Korea, Republic of), 29-30 May 1998; Other Information: PBD: 1998; Related Information: Is Part Of Proceedings of the korean nuclear society spring meeting vol I, May 29-30, 1998 Seoul, Korea; PB: 905 p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 22 NUCLEAR REACTOR TECHNOLOGY; TEMPERATURE CONTROL; TEMPERATURE MONITORING; NUCLEAR TEMPERATURE; REGULATIONS; YONGGWANG-3 REACTOR; YONGGWANG-4 REACTOR; REACTOR COOLING SYSTEMS; MODIFICATIONS; REACTOR OPERATION; FLEXIBILITY; SAFETY; ENGINEERED SAFETY SYSTEMS; REACTOR SAFETY; PRESSURIZERS; OPTIMIZATION; CONTROL SYSTEMS
OSTI ID:
325252
Research Organizations:
Korean Nuclear Society, Taejon (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
English
Other Identifying Numbers:
Other: ON: DE99732629; TRN: KR9900346
Availability:
OSTI as DE99732629
Submitting Site:
KR
Size:
pp. 404-410
Announcement Date:
Apr 06, 1999

Citation Formats

Yu, Sung Sik, Lee, Byung Jin, Kim, Se Chang, Cheong, Jong Sik, Kim, Ji In, and Doo, Jin Yong. Modification of reference temperature program in reactor regulating system. Korea, Republic of: N. p., 1998. Web.
Yu, Sung Sik, Lee, Byung Jin, Kim, Se Chang, Cheong, Jong Sik, Kim, Ji In, & Doo, Jin Yong. Modification of reference temperature program in reactor regulating system. Korea, Republic of.
Yu, Sung Sik, Lee, Byung Jin, Kim, Se Chang, Cheong, Jong Sik, Kim, Ji In, and Doo, Jin Yong. 1998. "Modification of reference temperature program in reactor regulating system." Korea, Republic of.
@misc{etde_325252,
title = {Modification of reference temperature program in reactor regulating system}
author = {Yu, Sung Sik, Lee, Byung Jin, Kim, Se Chang, Cheong, Jong Sik, Kim, Ji In, and Doo, Jin Yong}
abstractNote = {In Yonggwang nuclear units 3 and 4 currently under commercial operation, the cold temperature was very close to the technical specification limit of 298 deg C during initial startup testing, which was caused by the higher-than-expected reactor coolant system flow. Accordingly, the reference temperature (Tref) program needed to be revised to allow more flexibility for plant operations. In this study, the method of a specific test performed at Yonggwang nuclear unit 4 to revise the Tref program was described and the test results were discussed. In addition, the modified Tref program was evaluated on its potential impacts on system performance and safety. The methods of changing the Tref program and the associated pressurizer level setpoint program were also explained. Finally, for Ulchin nuclear unit 3 and 4 currently under initial startup testing, the effects of reactor coolant system flow rate on the coolant temperature were evaluated from the thermal hydraulic standpoint and an optimum Tref program was recommended. 6 refs., 4 figs., 2 tabs. (Author)}
place = {Korea, Republic of}
year = {1998}
month = {Dec}
}