TY - GEN
T1 - EVALUATION OF EFFECT OF DEPRESSURIZATION TIMING ON THE THERMAL LOAD TO PRIMARY CONTAINMENT VESSEL DURING SEVERE ACCIDENT AT BWR
AU - Matsumoto, Taisei
AU - Yamaji, Akifumi
AU - Fujiwara, Daisuke
N1 - Funding Information:
This work was partly supported by JSPS KAKENHI Grant Number 20H02669. A part of this study is the result of “Understanding Mechanisms of Severe Accidents and Improving Safety of Nuclear Reactors by Computer Science” of Waseda Research Institute for Science and Engineering and the authors acknowledge support of the Institute for Advanced Theoretical and Experimental Physics, Waseda University.
Publisher Copyright:
Copyright © 2022 by ASME.
PY - 2022
Y1 - 2022
N2 - According to accident of a Boiling Water Reactor (BWR), the operators generally do not depressurize the Reactor Pressure Vessel (RPV) until low-pressure core injection systems are recovered. However, when the core water level decreases below a certain limit, the RPV is depressurized to prevent the RPV failure at high pressure, which may lead to failure of the Primary Containment Vessel (PCV) by direct heating of the ejected melt. In such a case, if recovery of the core cooling cannot be expected, earlier depressurization may be preferable from the viewpoint of reducing thermal load on PCV, because it may effectively reduce the amount of fission product (FP) aerosol deposition on the RPV dome and reduce the risk of PCV top head heating via convective and radiative heat transfers from the RPV dome. However, significance of such risk is not evident as the steam dryer and separator may hinder direct aerosol deposition on the RPV dome and the RPV dome is thermally insulated. Moreover, the narrow space between the RPV dome and the PCV top head may hinder convective heat transfer. In this study, sensitivity analyses have been carried out using MELCOR-2.2 to support such understanding.
AB - According to accident of a Boiling Water Reactor (BWR), the operators generally do not depressurize the Reactor Pressure Vessel (RPV) until low-pressure core injection systems are recovered. However, when the core water level decreases below a certain limit, the RPV is depressurized to prevent the RPV failure at high pressure, which may lead to failure of the Primary Containment Vessel (PCV) by direct heating of the ejected melt. In such a case, if recovery of the core cooling cannot be expected, earlier depressurization may be preferable from the viewpoint of reducing thermal load on PCV, because it may effectively reduce the amount of fission product (FP) aerosol deposition on the RPV dome and reduce the risk of PCV top head heating via convective and radiative heat transfers from the RPV dome. However, significance of such risk is not evident as the steam dryer and separator may hinder direct aerosol deposition on the RPV dome and the RPV dome is thermally insulated. Moreover, the narrow space between the RPV dome and the PCV top head may hinder convective heat transfer. In this study, sensitivity analyses have been carried out using MELCOR-2.2 to support such understanding.
KW - accident management procedure
KW - Boiling Water Reactor (BWR) severe accident
KW - fission product behavior
KW - MELCOR
UR - http://www.scopus.com/inward/record.url?scp=85143133870&partnerID=8YFLogxK
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U2 - 10.1115/ICONE29-90648
DO - 10.1115/ICONE29-90648
M3 - Conference contribution
AN - SCOPUS:85143133870
SN - 9784888982566
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
BT - Mitigation Strategies for Beyond Design Basis Events
PB - American Society of Mechanical Engineers (ASME)
T2 - 2022 29th International Conference on Nuclear Engineering, ICONE 2022
Y2 - 8 August 2022 through 12 August 2022
ER -