Development of Time Dependent Safety Analysis Code for Plasma Anomaly Events in Fusion Reactors.
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- HONDA Takuro
- Hitachi Research Laboratory Hitachi Ltd.
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- BARTELS H-W
- ITER Joint Central Team San Diego
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- UCKAN N. A.
- Oak Ridge National Laboratory
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- SEKI Yasushi
- Naka Fusion Research Establishment Japan Atomic Energy Research Institute
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- OKAZAKI Takashi
- Hitachi Research Laboratory Hitachi Ltd.
書誌事項
- タイトル別名
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- Development of Time Dependent Safety An
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A safety analysis code SAFALY has been developed to analyze plasma anomaly events in fusion reactors, e.g., a loss of plasma control. The code is a hybrid code comprising a zero-dimensional plasma dynamics and a one-dimensional thermal analysis of in-vessel components. The code evaluates the time evolution of plasma parameters and temperature distributions of in-vessel components. As the plasma-safety interface model, we proposed a robust plasma physics model taking into account updated data for safety assessment. For example, physics safety guidelines for beta limit, density limit and H-L mode confinement transition threshold power, etc. are provided in the model. The model of the in-vessel components are divided into twenty temperature regions in the poloidal direction taking account of radiative heat transfer between each surface of each region. This code can also describe the coolant behavior under hydraulic accidents with the results by hydraulics code and treat vaporization (sublimation) from plasma facing components (PFCs). Furthermore, the code includes the model of impurity transport form PFCs by using a transport probability and a time delay. Quantitative analysis based on the model is possible for a scenario of plasma passive shutdown. We examined the possibility of the code as a safety analysis code for plasma anomaly events in fusion reactors and had a prospect that it would contribute to the safety analysis of the International Thermonuclear Experimental Reactor (ITER).
収録刊行物
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- Journal of Nuclear Science and Technology(日本原子力学会英文論文誌)
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Journal of Nuclear Science and Technology(日本原子力学会英文論文誌) 34 (3), 229-239, 1997
一般社団法人 日本原子力学会
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詳細情報 詳細情報について
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- CRID
- 1390282679072766208
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- NII論文ID
- 10002076590
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- NII書誌ID
- AA00703720
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- COI
- 1:CAS:528:DyaK2sXivFWnurg%3D
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- ISSN
- 18811248
- 00223131
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- NDL書誌ID
- 4176274
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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
- NDL
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