确保材料组装中金属样品的辐照条件,以证明bn -600反应堆的寿命延长是合理的。

Е. С. Кирилова, А. А. Радионычева, М. Р. Фаракшин
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引用次数: 0

摘要

为了延长BN-600反应堆的运行寿命,有必要验证在高损伤剂量和高温条件下运行的永久性反应堆元件(包括中子反射器)的可操作性。它可以通过在BN-600中插入的材料科学组件内照射模拟封装的金属来实现。介绍了该装置的基本特点,包括设计特点和辐照参数。介绍了反应堆内材料科学组件和组件内样品选择位置的基本原则,以确保金属样品所需的辐照条件。通过对堆芯内和径向包层内材料科学装配位置的比较,讨论了材料科学装配位置对反应堆标准燃料组件特性和中子通量场的影响。为了计算辐照参数和位置对材料科学装配的影响,采用了与反应堆堆芯设计工作相同的方法和程序。材料科学组件对反应堆堆芯中子特性的影响已被证明是最小的,当组件插入径向包层时。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
ОБЕСПЕЧЕНИЕ УСЛОВИЙ ОБЛУЧЕНИЯ ОБРАЗЦОВ МЕТАЛЛА В СОСТАВЕ МАТЕРИАЛОВЕДЧЕСКОЙ СБОРКИ ДЛЯ ОБОСНОВАНИЯ ПРОДЛЕНИЯ СРОКА ЭКСПЛУАТАЦИИ РЕАКТОРА БН-600
In order to extend the operation life of the BN-600 reactor, it is necessary to validate operability of the permanent reactor elements – including the neutron reflector – that operate under the conditions with high damaging doses and high temperatures. It can be done through irradiating metal of simulating package inside a materials science assembly inserted in BN-600. The paper describes basic characteristics of the assembly, including design features and irradiation parameters. Described are the basic principles of selecting the location for the materials science assembly in the reactor and for specimens inside the assembly in order to ensure the required irradiation conditions for the metal specimens. With comparing the materials science assembly locations in the reactor core and in the radial blanket, the effect is discussed that the materials science assembly location has upon the characteristics of the reactor standard fuel assemblies and upon the neutron flux field. To calculate the irradiation parameters and the effect that the location has upon the materials science assembly, the same methods and programs are used as for the reactor core design work. The effect of the materials science assembly upon the reactor core neutronic characteristics has been shown to be minimum when the assembly is inserted in the radial blanket.
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