Name: Kori-3 Nuclear Power Reactor (고리 원자력발전소 3호기)
Location: Kori, Chang’an-ŭp, Kijang-kun, Pusan, South Korea
Address: 216 Kori, Chang’an-ŭp, Kijang-kun, Pusan 619-711, South Korea
Telephone Number: +82-51-726-2114
Subordinate to: Korea Hydro & Nuclear Power Co., Ltd. (한국수력원자력주)
Size: 950MW(e) pressurized water reactor (PWR)
Primary Function: Production of electricity
Description: Kori-3 is South Korea’s fifth nuclear power reactor. Construction for Kori-3 began in 1979 and the reactor began commercial operation in September 1985. Kori-3 is a three-loop pressurized light water reactor and its twin unit is the Kori-4 nuclear power reactor. Kori-3 is the first nuclear power reactor constructed under the second phase of South Korea’s nuclear power program called “the component approach,” in which foreign firms were contracted for the design and provision of main components while domestic firms were subcontracted for auxiliary components. In addition, to increase self-sufficiency in nuclear power plant construction and technology, the Korea Electric Power Corporation (KEPCO) expanded its participation by leading the overall construction project with assistance from foreign firms and allowing Korean firms to manage site construction. Kori-3 was constructed by Hyundai Heavy Industries and Construction (Hanjung) while Westinghouse Electric Corporation provided the reactor, and General Electric Company provided the steam generator. In 1992, Kori-3 moved from a 12-month to 15-month fuel cycle and then to an 18-month cycle in 1995.
Kori-3 has experienced several shut downs due to accidents and malfunctions. In October 1993, low water levels in the steam generator caused the turbine in the reactor to stop, resulting in a temporary shut down. In April 1999, Kori-3 was shut down for approximately 10 days due to problems with the cooling system and steam generator. Furthermore, in 1999, the Korea Institute of Nuclear Safety (KINS) reported the discovery of unidentified welded sections in Kori-3 and several nuclear power plants (?) that could cause pipe corrosion due to the boric acid contained in the coolant water.
Key sources: Ministry of Science and Technology, <http://www.most.go.kr>; Ministry of Science and Technology, Wŏnjaryŏk Anjŏnbaeksŏ (Seoul: MOST, 2003); Mark Hibbs, “All But Two Oldest Korean PWRs to Be on 18-Month Cycles by 2007,” Nuclear Fuel, 10 December 2001, p. 4, in Lexis-Nexis, <http://web.lexis-nexis.com>; “Kori Wŏnjŏn 3 Hogi Chŏngji/Pangsasŏn’gwanŭn Mu’gwan,” Donga Ilbo, 17 October 1993, p. 7, in KINDS, <http://www.kinds.or.kr>; Chosun Ilbo, 4 April 1999, in “Cooling System, Generator Trouble Close Kori Nuke Plant,” FBIS Document ID: FTS19990404000256; “Koriwŏnjŏn 3 Hogi Naenggakkyet’ong Kojang...Paljŏn Chungdan,” Munhwa Ilbo, 5 April 1999, p. 22, in KINDS, <http://www.kinds.or.kr>; Chosun Ilbo, 13 October 1999, in “Welding Found in Nuclear Reactors,” FBIS Document ID: FTS19991013001123; Kim Dong Wŏn, “Yŏnggwang-Uljinwŏnjŏn Tŭng Sangdangsu ‘Yongjŏpkyŏlham,” Segye Ilbo, 14 October 1999, p. 23, in KINDS, <http://www.kinds.or.kr>; “Ka’ap Kyŏngsuro,” Nuke.co.kr,<http://nuke.co.kr/energy/generation/interior/PWR.htm>.
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Updated September 2004 |
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