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Reload safety evaluation report for kori nuclear power plant unit 2 cycle 9

Technical Report:

Abstract

The Kori Nuclear Power Plant Unit 2 (Kori-2) is anticipated to be refuelled with 16x16 Korean Fuel Assemblies (KOFA), which are based on the KAERI design starting from Cycle 8. This report presents a reload safety evaluation for Kori-2, Cycle 9 and demonstrates that the reactor core being composed of various fuel assembly types as described below will not adversely affect the safety of the public and the plant. The evaluation of Kori-2, Cycle 9 was accomplished utilizing the methodology described in `Reload Transition Safety Report for KORI 2` (Ref. /1-1/). The reload core for Kori-2, Cycle 9 is entirely comprised of 16x16 KOFA. In the Kori-2 licensing documentation to KEPCO the reference safety evaluation was provided for the operation of a reactor core fully loaded with KOFA as well as associated proposed changes to the Kori-2 Technical Specifications. The reload for Kori-2, Cycle 9 also introduces UO{sub 2}/Gd{sub 2}O{sub 3} containing fuel rods. The use of fuel rods with Gd{sub 2}O{sub 3} poisoning of the fuel has been approved as a part of the above mentioned licensing documentation. All of the accidents comprising the licensing bases which could potentially be affected by the fuel reload have been reviewed for  More>>
Authors:
Cho, Beom Jin; Kim, Si Yong; Kim, Oh Hwan; Nam, Kee Il; Um, Gil Sup; Ban, Chang Hwan; Choi, Dong Uk; Yoon, Kyung Ho [1] 
  1. Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)
Publication Date:
Apr 01, 1992
Product Type:
Technical Report
Report Number:
KAERI/TR-266/92
Reference Number:
SCA: 210200; PA: AIX-25:006628; EDB-94:012337; ERA-19:006604; NTS-94:014834; SN: 94001126509
Resource Relation:
Other Information: PBD: Apr 1992
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; REACTOR FUELING; CONTROL ROD WORTHS; DESIGN; FLOW RATE; FUEL RODS; GADOLINIUM OXIDES; POWER DENSITY; POWER DISTRIBUTION; REACTOR CORES; URANIUM DIOXIDE; 210200; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED
OSTI ID:
10113030
Research Organizations:
Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
English
Other Identifying Numbers:
Other: ON: DE94610816; TRN: KR9300126006628
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
32 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Cho, Beom Jin, Kim, Si Yong, Kim, Oh Hwan, Nam, Kee Il, Um, Gil Sup, Ban, Chang Hwan, Choi, Dong Uk, and Yoon, Kyung Ho. Reload safety evaluation report for kori nuclear power plant unit 2 cycle 9. Korea, Republic of: N. p., 1992. Web.
Cho, Beom Jin, Kim, Si Yong, Kim, Oh Hwan, Nam, Kee Il, Um, Gil Sup, Ban, Chang Hwan, Choi, Dong Uk, & Yoon, Kyung Ho. Reload safety evaluation report for kori nuclear power plant unit 2 cycle 9. Korea, Republic of.
Cho, Beom Jin, Kim, Si Yong, Kim, Oh Hwan, Nam, Kee Il, Um, Gil Sup, Ban, Chang Hwan, Choi, Dong Uk, and Yoon, Kyung Ho. 1992. "Reload safety evaluation report for kori nuclear power plant unit 2 cycle 9." Korea, Republic of.
@misc{etde_10113030,
title = {Reload safety evaluation report for kori nuclear power plant unit 2 cycle 9}
author = {Cho, Beom Jin, Kim, Si Yong, Kim, Oh Hwan, Nam, Kee Il, Um, Gil Sup, Ban, Chang Hwan, Choi, Dong Uk, and Yoon, Kyung Ho}
abstractNote = {The Kori Nuclear Power Plant Unit 2 (Kori-2) is anticipated to be refuelled with 16x16 Korean Fuel Assemblies (KOFA), which are based on the KAERI design starting from Cycle 8. This report presents a reload safety evaluation for Kori-2, Cycle 9 and demonstrates that the reactor core being composed of various fuel assembly types as described below will not adversely affect the safety of the public and the plant. The evaluation of Kori-2, Cycle 9 was accomplished utilizing the methodology described in `Reload Transition Safety Report for KORI 2` (Ref. /1-1/). The reload core for Kori-2, Cycle 9 is entirely comprised of 16x16 KOFA. In the Kori-2 licensing documentation to KEPCO the reference safety evaluation was provided for the operation of a reactor core fully loaded with KOFA as well as associated proposed changes to the Kori-2 Technical Specifications. The reload for Kori-2, Cycle 9 also introduces UO{sub 2}/Gd{sub 2}O{sub 3} containing fuel rods. The use of fuel rods with Gd{sub 2}O{sub 3} poisoning of the fuel has been approved as a part of the above mentioned licensing documentation. All of the accidents comprising the licensing bases which could potentially be affected by the fuel reload have been reviewed for the Cycle 9 core design described herein. (Author).}
place = {Korea, Republic of}
year = {1992}
month = {Apr}
}