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核融合動力プラントの安全性についての考察

Consideration for the safety of a fusion power plant

小西 哲之

Konishi, Satoshi

ITERの安全ロジックに基づいて、核融合動力プラントの安全性について考察した。ITERの方法論は核融合の原理的安全の本質に根ざしたものであり、多くの部分で動力プラントでも適用できる。即ち、放射性物質とエネルギーのソースタームを摘出し、そのハザードの大きさと経路を解析するものであり、核分裂と比較すればその規模と経路の遠さが対策を容易にしている。ITERと動力炉の最大の違いはトリチウムとエネルギーの共存するブランケットであり、インベントリーは同規模でありながらトリチウム処理系の性格が大きく異なる。大量トリチウム除去系が能動的に常時トリチウム放出を管理する特徴から、核融合プラントは異常時のためのシステムを特別に必要としない。

Based on the fundamental approach for safety of ITER, possible extension to assure safety of fusion power plant was considered. Although the entire analysis and licensing preparation are specific for ITER, its methodology that take full advantage of inherent feature of fusion is expected to be applied to fundamental logic of fusion power plant. Both energy and radioactive source terms that could be potential hazards are typically of order of days of operation rather than a year in the case of fission. Major difference from the test reactor ITER identified was power blanket, coolant loop and generator train that will hold high temperature and considerable amount of tritium. It is anticipated that tritium inventory and most of the tritium safety plant would essentially be same as ITER, tritium recovery and removal from blanket loop will dominate the fusion power plant tritium systems. Such a tritium system will actively remove tritium at the daily throughput comparable with the order of plant inventory. This feature suggest no dedicated off-normal systems are needed to assure safety of fusion plant from the aspect of environmental tritium release.

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