核反应堆混凝土主屏蔽层的温度和热应力分布

David R. Thomas
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引用次数: 8

摘要

分析了厚环形混凝土屏蔽层中辐射吸收引起的温度和热应力分布。最大允许入射能量通量与最大允许压缩应力或拉应力相关的设计准则被开发出来。对于412英尺厚的防护罩,典型的结果是最大允许入射能量通量为85 Btu/hr-ft2,导致防护罩内表面和外表面由工厂容器空气冷却的最高温升为95°F。结果实际上与入射辐射的性质无关,无论是中、高能伽玛还是中子。描述了用于研究钢和混凝土环空中核辐射吸收引起的热应力的Fortran数字计算机代码。当使用IBM 7090数字计算机执行计算时,可以在12秒内详细计算屏蔽中的温度和应力分布。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Temperature and thermal stress distributions in concrete primary shields for nuclear reactors

The distribution of temperature and thermal stresses arising from the absorption of nuclear radiation in thick annular concrete shields is analysed. Design criteria are developed relating maximum allowable incident energy fluxes to maximum allowable compression or tension stresses. A typical result for a 412 ft thick shield is a maximum allowable indicent energy flux of 85 Btu/hr-ft2, resulting in a maximum temperature rise of 95°F in a shield cooled by plant container air on both inner and outer surfaces. The results are virtually independent of the nature of the incident radiation whether medium or high energy gammas, or neutrons.

Stature, a Fortran digital computer code for the study of thermal stresses arising from the absorption of nuclear radiation in both steel and concrete annuli is described. Use of Stature allows detailed calculation of the temperature and stress distributions in a shield within 12 sec when the computation is performed with the IBM 7090 digital computer.

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