Role of Passive Safety Features in Prevention and Mitigation of Severe Plant Conditions in Indian Advanced Heavy Water Reactor

Vikas Jain; A. K. Nayak; M. Dhiman; P.P. KULKARNI; P. K. Vijayan; K.K. Vaze

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자료유형: 학술저널

저자정보: Vikas Jain A. K. Nayak M. Dhiman P.P. KULKARNI P. K. Vijayan K.K. Vaze

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제45권 제5호

발행연도: 2013.1

수록면: 625 - 636 (12page)

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Pressing demands of economic competitiveness, the need for large-scale deployment, minimizing the need of human intervention, and experience from the past events and incidents at operating reactors have guided the evolution and innovations in reactor technologies. Indian innovative reactor ‘AHWR’ is a pressure-tube type natural circulation based boiling water reactor that is designed to meet such requirements, which essentially reflect the needs of next generation reactors. The reactor employs various passive features to prevent and mitigate accidental conditions, like a slightly negative void reactivity coefficient, passive poison injection to scram the reactor in event of failure of the wired shutdown systems, a large elevated pool of water as a heat sink inside the containment, passive decay heat removal based on natural circulation and passive valves, passive ECC injection, etc. It is designed to meet the fundamental safety requirements of safe shutdown, safe decay heat removal and confinement of activity with no impact in public domain, and hence, no need for emergency planning under all conceivable scenarios. This paper examines the role of the various passive safety systems in prevention and mitigation of severe plant conditions that may arise in event of multiple failures. For the purpose of demonstration of the effectiveness of its passive features, postulated scenarios on the lines of three major severe accidents in the history of nuclear power reactors are considered, namely; the Three Mile Island (TMI), Chernobyl and Fukushima accidents. Severe plant conditions along the lines of these scenarios are postulated to the extent conceivable in the reactor under consideration and analyzed using best estimate system thermal-hydraulics code RELAP5/Mod3.2. It is found that the various passive systems incorporated enable the reactor to tolerate the postulated accident conditions without causing severe plant conditions and core degradation.

#Passive Safety #AHWR #Severe Plant Condition #Fukushima #Chernobyl #Three Mile Island

참고문헌 (9)

참고문헌 신청

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