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Overview of ARIES-RS neutronics and radiation shielding: key issues and main conclusions

L.A El-Guebaly, The ARIES Team1997年Fusion Engineering and DesignIF 1.7出版社

AbstractThe neutronics and radiation shielding issues were assessed for the ARIES-RS power plant. The assessment addresses the breeding level, service lifetime, radiation damage, shielding requirements and design, and personnel protection. Major efforts were devoted to fulfil the top-level requirements which include the demonstration of a closed tritium fuel cycle, generation of no radioactive waste greater than Class C, and production of electricity at a competitive cost. The material optimization was one of the themes of this study as it influences the neutronics results and helps meet the requirements while minimizing cost. An important outcome of the neutronics and shielding analyses is the specification of the radial builds that contain key component parameters in terms of sizes and optimal compositions. The shielding system comprises a major element of the fusion power core (FPC). The primary function of the shield is radiation protection: protection of superconducting magnets, vacuum vessel, workers and the public. As an element of the power core, the bulk shield meets other requirements for power production and service lifetime. In addition, it serves as a heat sink for the FW/blanket decay heat during a loss-of-coolant accident. All shielding elements are integrated with the remainder of the FPC to meet the assembly, mechanical support and attachments, and maintenance requirements. The system requirements developed for the shield stem from these essential shielding functions. The work reported herein illustrates the strong impact of numerous factors (such as service lifetime, blanket segmentation, shield optimization, radial builds, and unit costs of materials) on the economics of power production.

日本語訳

核物理学および放射線防護の観点から、ARIES-RS発電プラントにおける中性子工学と放射線遮蔽の問題を評価した。この評価では、増殖比、サービス寿命、放射線損傷、遮蔽要件と設計、ならびに作業員の被ばく防護を取り扱う。主要な努力は、閉ループトリチウム燃料サイクルの実証、クラスCを超える放射性廃棄物の発生ゼロ、および競争力のあるコストでの電力生産という上位レベルの要件を満たすことに注がれた。材料の最適化は、この研究のテーマの一つであり、中性子工学的結果に影響を与え、コストを最小化しつつ要件を満たすのに寄与した。中性子工学および遮蔽解析の重要な成果は、主要な構成要素の寸法と最適な組成を規定する半径方向のビルド(径方向構造)の仕様である。遮蔽システムは、核融合動力炉心(FPC)の主要な要素を構成する。遮蔽の主な機能は放射線防護であり、超伝導磁石、真空容器、作業員、および公衆を保護する。動力炉心の要素として、バルク遮蔽は電力生産とサービス寿命に関するその他の要件も満たす。さらに、冷却材喪失事故時におけるFW/ブランケットの崩壊熱のヒートシンクとしても機能する。すべての遮蔽要素は、組み立て、機械的支持、および保守の要件を満たすために、FPCの残りの部分と統合される。遮蔽のために開発されたシステム要件は、これらの本質的な遮蔽機能に由来する。本報告書で述べた研究は、サービス寿命、ブランケット分割、遮蔽最適化、径方向ビルド、および材料単価などの多くの要因が、電力生産の経済性に強く影響することを示している。

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