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Neutronic shielding analysis of the water-cooled lithium lead test blanket module in the ITER machine

M Rapisarda2000年Fusion Engineering and DesignIF 1.7出版社

AbstractDuring the operations of the next experimental fusion machine three breeding test blanket modules (TBM) for a power reactor will be inserted in the horizontal ports and their performance examined. The insertion will change the overall shielding capability of the structure and thus the regular operability of the machine could be affected. In this paper, I report the Monte Carlo simulations made to account for the water-cooled lithium lead TBM insertion in the international thermonuclear experimental reactor (ITER) machine. A 9° torus sector of ITER is modelled comprising a detailed description of the TBM located in position, with an additional shield in the back. Results show that the present project of the WCLL TBM, with an additional backshield, is suitable for testing in ITER and does not interfere with the regular operations of the machine.

日本語訳

次期実験核融合装置の運転中に、動力炉用の3つの増殖試験ブランケットモジュール(TBM)が水平ポートに挿入され、その性能が検証される予定である。この挿入により、装置全体の遮蔽能力が変化し、その結果、装置の通常運転に影響が及ぶ可能性がある。本論文では、国際熱核融合実験炉(ITER)装置における水冷リチウム鉛TBMの挿入を考慮して実施したモンテカルロシミュレーションについて報告する。ITERの9度トーラスセクターをモデル化し、追加の背面遮蔽体を備えたTBMの詳細な記述を所定の位置に含めた。結果は、追加の背面遮蔽体を備えた現在のWCLL TBM設計が、ITERでの試験に適しており、装置の通常運転を妨げないことを示している。

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ITERLithiumTest blanket moduleLead-lithium eutecticShieldingBlanket module
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