TY - GEN
T1 - ESTIMATION OF THE 1F2 CORE THERMAL STATUS DURING THE CORE HEAT-UP PHASE WITH MELCOR-2.2
AU - Osako, Shotaro
AU - Li, Xin
AU - Yamaji, Akifumi
N1 - Funding Information:
A part of this work was supported by Nuclear Energy Science &Technology and Human Resource Development Project of Japan. 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 - For decommissioning of the Unit 2 of Fukushima Daiichi Nuclear Power Station (1F2), more supportive information is necessary regarding the debris distributions and characteristics as complementary to what has been gained through internal investigations. The current debris status is expected to have been greatly affected by the peak core energy (temperature) during the core heat-up phase, before collapsing (slumping) to the lower plenum of the reactor pressure vessel (RPV), at the time of the accident. In another word, whether the oxidic fuel melted in the core region or not. Such supportive information can be gained through detailed analyses of the plant data and the corresponding accident progression analyses. In this study, accident progression analyses of 1F2 were performed considering uncertainty of the core oxidation and the impact of the leakage from the RPV to the D/W on the estimated core energy with the severe accident analysis code MELCOR-2.2. The best estimate case successfully reproduced RPV and D/W pressure histories and showed that the peak core temperature was about 2700 K. This indicated that large-scale melting of the oxidic fuel in the core region was unlikely in 1F2, although some local oxidic fuel melting may have taken place.
AB - For decommissioning of the Unit 2 of Fukushima Daiichi Nuclear Power Station (1F2), more supportive information is necessary regarding the debris distributions and characteristics as complementary to what has been gained through internal investigations. The current debris status is expected to have been greatly affected by the peak core energy (temperature) during the core heat-up phase, before collapsing (slumping) to the lower plenum of the reactor pressure vessel (RPV), at the time of the accident. In another word, whether the oxidic fuel melted in the core region or not. Such supportive information can be gained through detailed analyses of the plant data and the corresponding accident progression analyses. In this study, accident progression analyses of 1F2 were performed considering uncertainty of the core oxidation and the impact of the leakage from the RPV to the D/W on the estimated core energy with the severe accident analysis code MELCOR-2.2. The best estimate case successfully reproduced RPV and D/W pressure histories and showed that the peak core temperature was about 2700 K. This indicated that large-scale melting of the oxidic fuel in the core region was unlikely in 1F2, although some local oxidic fuel melting may have taken place.
KW - core oxidation, MELCOR-2.2
KW - fuel debris characteristics
KW - Fukushima Daiichi NPS Unit-2 (1F2)
KW - severe accident analysis
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U2 - 10.1115/ICONE29-89102
DO - 10.1115/ICONE29-89102
M3 - Conference contribution
AN - SCOPUS:85143169981
SN - 9784888982566
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
BT - Thermal-Hydraulics and Safety Analysis
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 -