用混凝土屏蔽高温反应堆

V.B. Dubrovskii, N.V. Krasnoyarov, M.Ya. Kulakovskii, B.K. Pergamenshchik, M.S. Pinkhasik, V.I. Savitskii
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引用次数: 3

摘要

探讨了用铬铁矿和耐火粘土耐热混凝土构筑反应堆隔热罩的可能性。研究了这些材料屏蔽层吸收的不同强度的中子通量(高达1013 n/cm2秒,在光谱上接近裂变光谱)。考虑了中子的通过、y射线通量和热在屏蔽层中的产生。计算了不同中子通量、混凝土厚度和冷却条件下屏蔽层的温度。本文对隔热钢筋混凝土盾构的温度应力进行了静力计算。研究表明,耐热钢筋混凝土可用于核反应堆的防护层,其中子通量可达1013 n/cm2秒,温度可达1000 ~ 1100℃,温度降可达900℃。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
The use of concrete for shielding high-temperature reactors

The possibility is examined of constructing thermal shields of reactors from chromite and fireclay heat-resistant concretes. Neutron fluxes of different intensities (up to 1013 n/cm2 sec, close in spectrum to the fission spectrum) absorbed by shields of these materials are examined. The passage of neutrons, y-ray fluxes and generation of heat in the shield are taken into account. The temperatures in the shield are calculated for different neutron fluxes, thicknesses of concrete and cooling conditions. A static calculation of the temperature stresses in a shield constructed from heat-proof reinforced concrete is carried out.

It is established that heat-resistant reinforced concrete can be used for the shields of nuclear reactors for neutron fluxes to the concrete up to 1013 n/cm2 sec, temperatures up to 1000–1100°C and temperature drops of up to 900°C.

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