The Effects of Thermal Aging on Material Behavior and Strength of CF8M in Nuclear Reactor Coolant System

机译：热老化对核反应堆冷却剂系统CF8M材料性能和强度的影响

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A stainless steel casting is used in pipes and values subjected to high pressure and temperature. The primary coolant system of a nuclear power plant is made of a stainless steel casting and the operating temperature is in the range of 290 approx 330 deg C. If the coolant system is exposed to this temperature range for a long period, it may be possible to experience degradation of the material.

机译：管道中使用不锈钢铸件，其值承受高压和高温。核电站的一次冷却液系统由不锈钢铸件制成，工作温度在290左右（330摄氏度）范围内。如果冷却液系统长时间暴露在该温度范围内，则可能经历材料的降解。

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《International conference on structural mechanics in reactor technology;SMiRT-15》|1999年|p.X-189-196|共1页
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Jae-Do Kwon; Joong-Cheul Park; Yong-Son Lee; Woo-Ho Lee; Yun-Won Park;
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中图分类原子能技术;
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4. The Effects of Thermal Aging on Material Behavior and Strength of CF8M in Nuclear Reactor Coolant System [C] . Jae-Do Kwon, Joong-Cheul Park, Yong-Son Lee, International conference on structural mechanics in reactor technology . 1999

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The Effects of Thermal Aging on Material Behavior and Strength of CF8M in Nuclear Reactor Coolant System

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