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Safety analysis of the US dual coolant liquid lead–lithium ITER test blanket module

Brad Merrill, Susana Reyes, Mohamed Sawan, Clement Wong2007年被引用 8Nuclear FusionIF 3出版社

The US is proposing a prototype of a dual coolant liquid lead–lithium DEMO blanket concept for testing in the International Thermonuclear Experimental Reactor (ITER) as an ITER test blanket module (TBM). Because safety considerations are an integral part of the design process to ensure that this TBM does not adversely impact the safety of ITER, a safety assessment has been conducted for this TBM and its ancillary systems as requested by the ITER project. Four events were selected by the ITER international team (IT) to address specific reactor safety concerns, such as vaccum vessel (VV) pressurization, confinement building pressure build-up, TBM decay heat removal capability, tritium and activation products release from the TBM system and hydrogen and heat production from chemical reactions. This paper summarizes the results of this safety assessment conducted with the MELCOR computer code.

日本語訳

米国は、国際熱核融合実験炉(ITER)のテストブランケットモジュール(TBM)としてITERで試験するための、デュアルクーラント液体鉛リチウムDEMOブランケット概念のプロトタイプを提案している。安全上の考慮事項は、このTBMがITERの安全性に悪影響を及ぼさないことを確実にするための設計プロセスの不可欠な部分であるため、ITERプロジェクトの要請に応じて、このTBMとその補助システムの安全評価が実施された。ITER国際チーム(IT)は、真空容器(VV)の加圧、格納建屋の圧力上昇、TBMの崩壊熱除去能力、TBMシステムからのトリチウムおよび活性化生成物の放出、化学反応による水素と熱の生成など、特定の原子炉安全上の懸念に対処するために4つの事象を選択した。本論文は、MELCORコンピュータコードを用いて実施されたこの安全評価の結果を要約する。

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ITERLithiumTest blanket moduleLead-lithium eutecticBlanket module
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