Study on drywell cooler applicability to severe accident management

Conference · Thu Jul 01 00:00:00 EDT 2004

OSTI ID:21160572

Nakagawa, Takahiro ^[1]; Akinaga, Makoto ^[2]; Hamazaki, Ryoichi ^[3]; Matsuo, Toshihiro ^[4]; Hashimoto, Kouji ^[5]

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1. Information and manufacturing systems division, Toshiba Plant Systems and Services Corporation, 8, Shinsugita-cho, Isogo-ku, Yokohama, 235-8523 (Japan)
2. Power and Industrial Systems R and D Center, Toshiba Corporation, 4-1 Ukishima-cho, Kawasaki-ku, Kawasaki, 210-0862 (Japan)
3. Isogo Nuclear Engineering Center, Toshiba Corporation, 8, Shinsugita-cho, Isogo-ku, Yokohama, 235-8523 (Japan)
4. Nuclear Power Engineering Department, Tokyo Electric Power Company, 1-3 Uchisaiwai-cho 1-chome, Chiyoda-ku, Tokyo 100-0011 (Japan)
5. Nuclear Plant Engineering Department, HITACHI, Ltd., 1-1, Saiwai-cho, 3-chome, Hitachi-shi, Ibaraki-ken, 317-8511 (Japan)

This paper concerns applicability of drywell cooler (DWC) heat removal under severe accident condition in BWR plants. Newly developed heat removal models based on DWC heat removal experiments were built into the MAAP3 code. And then, two types of Japanese BWR were selected to evaluate DWC heat removal performance under typical severe accident scenarios. According to the results of the evaluation, DWC delays or prevents containment failure or venting. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 21160572
• Resource Relation: Conference: ICAPP'04: 2004 international congress on advances in nuclear power plants, Pittsburgh, PA (United States), 13-17 Jun 2004; Other Information: Country of input: France; 5 refs; Related Information: In: Proceedings of the 2004 international congress on advances in nuclear power plants - ICAPP'04, 2338 pages.
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
AFTER-HEAT REMOVAL
BWR TYPE REACTORS
CONTAINMENT
EVALUATION
FAILURES
HEAT
HEAT EXCHANGERS
MANAGEMENT
PERFORMANCE
REACTOR ACCIDENTS