Neutron studies of the V-4Ti-4Cr alloy

S. Bogdanov, I. F. Berger, V. Bobrovskii, V. Voronin, V. D. Parkhomenko, V. Chernov
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引用次数: 0

Abstract

Competitive economic indicators for fast-neuron power reactors can be achieved with high coefficients of fuel burnout, which requires remarkable enhancement of radiation resistance of fuel pin claddings. Nowadays, low-activation vanadium alloys are projected as promising fuel cladding materials in view of their high radiation and thermal resistance in wide temperature and damage dose ranges. Neutron diffraction and small-angle neutron scattering are employed to study the microstructure of the V-4Ti-4Cr alloy subjected to irradiation with fast neutrons in the fluence range up to 1·1020 cm−2. Minor phases precipitated in the system are structurally characterized. The applicability and prospects of neutron diffraction methods in terms of studying the radiation behavior of this kind of alloys are shown.
V-4Ti-4Cr合金的中子研究
高燃料燃尽系数可以实现具有竞争力的快神经元动力堆经济指标,这就要求燃料销包壳的抗辐射性能得到显著提高。目前,低活化钒合金因其在较宽的温度和损伤剂量范围内具有较高的辐射和耐热性,被认为是一种很有前途的燃料包壳材料。利用中子衍射和小角中子散射研究了快中子辐照下V-4Ti-4Cr合金的微观结构。体系中析出的少量相具有结构特征。指出了中子衍射方法在研究该类合金辐射行为方面的适用性和应用前景。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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