Development of a three-dimensional transient code for reactivity-initiated events of boiling water reactors; Two rod drop accident analyses

Journal Article · Mon Jan 01 04:00:00 EST 1990 · Nuclear Technology; (USA)

OSTI ID:6738563

Izutsu, S ^[1]; Kudo, Y ^[2]; Onuma, J ^[3]; Iwasaki, T ^[4]; Muto, S; Toba, A ^[5]

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1. Hitachi Ltd., Ibaraki (Japan). Hitachi Works
2. Nippon Atomic Industry Group Co. Ltd., Kawasaki, Kanagawa (Japan)
3. Hitachi Engineering Co. Ltd., Ibaraki (Japan)
4. Tohoku Univ., Sendai (Japan). Faculty of Engineering
5. Tokyo Electric Power Co., Inc. (Japan)

Rod drop accidents (RDAs) have been calculated for a typical 1100-MW (electric) boiling water reactor (BWR) using a three-dimensional core dynamics simulation code. Calculated cases are for cold-start-up and hot standby cores. In both cold start-up and hot standby core RDAs, the moderator density reactivity feedback has an important effect on suppressing fuel enthalpy increase. Hot standby core RDAs, in particular, show remarkable effects on the moderator density reactivity feedback on reducing the power peak and succeeding fuel enthalpy rise. Sensitivity analyses of the effects of initial power level, core inlet subcooling, rod drop speed, dropping rod worth, etc., have been carried out under both cold start-up and hot standby core conditions for a typical 1100-MW (electric) BWR. Results are presented in this paper.

• OSTI ID: 6738563
• Journal Information: Nuclear Technology; (USA), Journal Name: Nuclear Technology; (USA) Vol. 89:1; ISSN NUTYB; ISSN 0029-5450
• Country of Publication: United States
• Language: English

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