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Experience of Beryllium Blocks Operation in the SM and MIR Nuclear Reactors useful for Fusion

机译:在SM和MIR核反应堆中进行铍块操作的经验,可用于融合

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The results are presented concerning the examinations of state of beryllium blocks after the completion of their operation in the SM and MIR reactors. Both cracks and more significant mechanical damages are revealed in the irradiated beryllium blocks. Under neutron irradiation of beryllium radiation degradation of its physical and mechanical properties occurs. It shows itself in embrittlement, decrease of brittle strength level as well in worsening of thermal conductivity that leads to increase of thermal stresses into beryllium block. Under irradiation it takes place damage of beryllium microstructure, in particular, formation of radiation defects occurs in the form of dislocation loops and great amount of helium atoms. Optimization of beryllium radioactive waste storage is related to their preliminary surface and volumetric decontamination.
机译:结果提出了在SM和MIR反应器的操作完成后铍块状态的检查。在辐照的铍块中揭示了裂缝和更大的机械损伤。在中子照射的铍辐射劣化其物理和机械性能。它在脆化方面表现出脆性强度水平的降低以及导热率的热导电率的增加,导致热应力增加到铍块中。在照射下,它发生铍微观结构的损伤,特别是,辐射缺陷的形成以位错环和大量的氦原子。铍放射性废物储存的优化与其初步表面和体积净化有关。

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