An investigation of corium in Fukushima Daiichi Unit-1 accident
The core melt composition resulting from the Fukushima Daiichi Unit1 Nuclear Power Plant (FD-U1) accident is essential for the corium characterization phase before decommissioning or handling of radioactive waste. Several models were applied by different research groups for the estimation of corium...
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Published in | Applied radiation and isotopes Vol. 186; p. 110264 |
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Main Authors | , , , |
Format | Journal Article |
Language | English |
Published |
England
Elsevier Ltd
01.08.2022
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Subjects | |
Online Access | Get full text |
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Summary: | The core melt composition resulting from the Fukushima Daiichi Unit1 Nuclear Power Plant (FD-U1) accident is essential for the corium characterization phase before decommissioning or handling of radioactive waste. Several models were applied by different research groups for the estimation of corium composition. In this paper, the investigation of the isotopic composition, and radioactivity of the radio-nuclides in the corium10 and 50 years post-accident were calculated using Monte Carlo code, MCNPX 2.7.
The results showed that the estimated core materials inventory at reactor scram before core melt was about 123.97 ton, and after the formation of the corium melt was about 140.702 ton, which agrees with the predictions calculated using other models. Also, the total corium activity was about 6.046E+17 Bq and 1.89E+17 Bq 10 and 50 years post- accident, respectively. The radionuclide compositions in the corium are necessary for decommissioning plan of F-D-U1.
Furthermore, RELAP/SCDAPSIM MOD3.4 code was used for the analysis of thermal performance of the FD-U1 reactor core starting from the time of the accident up to corium formation and slumping to the lower head of the reactor pressure vessel (RPV). Our analysis indicates that the hydrogen generation started on March11th, around 18:39. The results were compared with MELCOR code and OECD/NEA BSAF Phase I results, which were found in good agreement.
•The corium formation and characterization in case of severe accident were reviewed.•Fukushima Daiichi Unit-1 accident was modeled using MCNPX and RELAP/SCDAPISM codes.•The corium inventory and radioactivity were calculated 10 and 50 years post- accident.•Additional heat in the core due to the exothermic reaction between zirconium and steam. |
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Bibliography: | SourceType-Other Sources-1 content type line 63 ObjectType-Correspondence-1 |
ISSN: | 0969-8043 1872-9800 |
DOI: | 10.1016/j.apradiso.2022.110264 |