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引用次数: 65

摘要

CrMo铁素体(马氏体)钢是未来核聚变反应堆结构部件的主要候选材料。然而,这种钢在核聚变环境中辐照会产生长寿命的放射性同位素,一旦结构停止使用,就会导致难以处理的废物问题。缓解这些问题的一种方法是开发只含有产生放射性同位素的元素的钢,这些元素会在合理的时间内(几十年而不是几百年或几千年)衰变到低水平。对于CrMo钢的这种溶液,必须去除钼。此外,铌必须保持在极低的水平。提出钨是钼的合适替代品,并讨论了类似于CrMo钢的CrW钢的制备方法。
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The development of ferritic steels for fast induced-radioactivity decay for fusion reactor applications

The CrMo ferritic (martensitic) steels are leading candidates for the structural components for future fusion reactors. However, irradiation of such steels in a fusion environment produces long-lived radioactive isotopes that lead to difficult waste disposal problems once the structure is removed from service. One method proposed to alleviate such problems is the development of steels that contain only elements that produce radioactive isotopes that decay to low levels in a reasonable time (tens of years instead of hundreds or thousands of years). For such a solution for the CrMo steels, molybdenum must be eliminated. In addition, niobium must be maintained at extremely low levels. Tungsten is proposed as an appropriate substitution for molybdenum, and the procedures for developing CrW steels analogous to the CrMo steels are discussed.

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Preface Announcement Cryopumping for fusion reactors 2.1. Development of low activation Al alloys for the R-project 6. Research and development on the tritium handling technology in the R-project
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