Japan's Efforts to Develop the Concept of JA DEMO During the Past Decade
抄録
This paper summarizes the evolution of Japanese DEMO design studies in a retrospective manner by highlighting efforts to resolve critical design issues on DEMO. Japan is currently working on the conceptual study of a steady state DEMO (JA DEMO) with a major radius of 8.5 m and fusion power of 1.5-2 GW based on water-cooled solid breeding (WCSB) blanket with PWR water condition (290-325ºC, 15.5 MPa). Such a lower Pfus allows to find realistic design solutions for divertor heat removal. Recognizing that divertor heat removal is one of the most challenging issues on DEMO, divertor design has been carried out in different approaches including numerical divertor plasma simulation, magnetic configurations, heat sink design, etc. It is noteworthy that the latest divertor simulation led to a design window allowing divertor heat removal of the peak heat flux of < 10 MW/m2. Breeding blanket (BB) design has been concentrated on simplification of the internal structure and pressure tightness of BB casing against in-box LOCA (Loss Of Coolant Accident). Due to a large amount of radioactive waste generated in periodic replacement of in-vessel components, downsizing of waste-related facilities came to be regarded as a significant design issue. A possible waste management for reducing temporary waste storage was proposed and its impact on the plant layout was assessed.
収録刊行物
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- Fusion Science and Technology
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Fusion Science and Technology 75 372-383, 2019-06
Taylor and Francis
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詳細情報 詳細情報について
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- CRID
- 1050564288426222720
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- NII論文ID
- 120006712769
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- ISSN
- 15361055
- 19437641
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- 本文言語コード
- en
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- 資料種別
- journal article
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- データソース種別
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- IRDB
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