EXPERIMENTAL STUDY ON ACCIDENT SOURCE TERMS TRANSPORT AND DEPOSITION BEHAVIOR IN NUCLEAR POWER PLANTS
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- Hosan Md. Iqbal
- Department of Applied Quantum Physics & Nuclear Engineering, Kyushu University, Fukuoka, Japan & Department of Nuclear Engineering, University of Dhaka
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- Koga Mizuki
- Department of Applied Quantum Physics & Nuclear Engineering, Kyushu University
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- Kakoi Akihiro
- Department of Applied Quantum Physics & Nuclear Engineering, Kyushu University
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- Morita Koji
- Department of Applied Quantum Physics & Nuclear Engineering, Kyushu University
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- Liu Wei
- Department of Applied Quantum Physics & Nuclear Engineering, Kyushu University
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- Cheng Xu
- Institute of Applied Thermofluidics, Karlsruhe Institute of Technology
説明
<p>Fukushima Daiichi Nuclear Power Plant accident resulted in a core meltdown, releasing a large amount of radioactive materials into the environment. This accident has reconfirmed the necessity and importance of the further in-depth development of core damage assessment technology (Level 2 PSA). In order to advance the core damage assessment technology, it is necessary to establish a source term migration assessment method through leak paths. We have started basic studies on the fission product (FP) migration behavior through leak paths, aiming to develop an evaluation method for aerosol transport based on transport mechanisms. In this paper, we will report basic decontamination factor (DF) data in narrow circular channels that simulate leak paths through containment vessel (CV) and reactor building. An experimental line is set up, and the experiments are performed under conditions simulate the environmental and flow conditions in the CV penetrations and failure locations at severe accident (SA). The tests are conducted to find the effects of flow path size and particle size on the DFs. DFs are derived from the experimental measurement of the aerosol concentrations at the inlet and outlet of the test sections. The obtained experimental DFs were compared with the existing models developed for aerosol deposition, considering the particle size distributions.</p>
収録刊行物
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- Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE
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Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE 2023.30 (0), 1806-, 2023
一般社団法人 日本機械学会
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詳細情報 詳細情報について
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- CRID
- 1390861228320064128
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- ISSN
- 24242934
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- 本文言語コード
- en
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- データソース種別
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- JaLC
- Crossref
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- 抄録ライセンスフラグ
- 使用不可