Abstract

The paper describes the results of post-irradiation examinations for pressurized specimens that varied in design and were made of austenitic steels 08Х18Н10Т and 07Х16Н12М3Т. They were under irradiation testing in the BOR-60 reactor to attain different damage dose values. The contribution of irradiation creep to the overall change in diameter was studied. Irradiation creep moduli data were obtained for austenitic steels 08Х18Н10Т and 07Х16Н12М3Т at the stage of steady-state creep in the damage dose range of 5–90 dpa.

中文翻译：

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在330至350°С温度范围内在BOR-60反应堆中辐照的钢08Х18Н10Т和07Х16Н12М3Т的辐照蠕变行为

摘要

本文描述了采用奥氏体钢08Х18Н10Т和07Х16Н12М3Т设计的加压试样的辐照后检查结果。他们在BOR-60反应堆中进行了辐射测试，以达到不同的破坏剂量值。研究了辐照蠕变对直径总体变化的贡献。在稳态蠕变阶段，在5–90 dpa的损伤剂量范围内，获得了奥氏体钢08Х18Н10Т和07Х16Н12М3Т的辐照蠕变模量数据。