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首页> 外文会议>Effects of radiation on nuclear materials and the nuclear fuel cycle >Irradiation-Induced Grain-Boundary Solute Segregation and Its Effect on Ductile-to-Brittle Transition Temperature in Reactor Pressure Vessel Steels
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Irradiation-Induced Grain-Boundary Solute Segregation and Its Effect on Ductile-to-Brittle Transition Temperature in Reactor Pressure Vessel Steels

机译：辐照诱导的晶粒边界溶质偏析及其对反应器压力容器钢中韧性对脆性转变温度的影响

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摘要

A study on grain-boundary segregation and embrittlement in terms of the Charpy ductile-to-brittle transition temperature (DBTT) has been performed for the neutron-irradiated A533B steels with typical contents of impurities of Japanese reactor pressure vessel ones. The neutron irradiation was conducted at 563 K to a fluence of 1.3X 1024n/m2 (?>1 MeV) using material testing reactors. The neutron irradiation induced the P and Ni segregation and the reduction in C in some cases at grain-boundaries. The increase in the P segregation at high fluence (>5X10 23n/m2, E>1 MeV) was less than 0.1 in monolayer coverage for the steels with the bulk content of P not exceeding 0.02 wt%. The hardening more strongly affected the DBTT shift than the P segregation for those steels. The reduction in segregated C that enhances the grain-boundary cohesion by neutron fluence is not large enough to cause the DBTT shift.
机译：对夏氏延性转变过渡温度（DBTT）的晶界偏析和脆化的研究已经对中子辐照的A533B钢进行了具有典型的日本反应器压力容器压力容器杂质的含量。使用材料检测反应器，在563k至1.3×1024N / m 2（ω> 1mev）的流量下进行中子辐射。中子辐射在晶界的一些病例中诱导p和ni偏析和C的含量减少。高流量（> 5×10 23N / m 2，e> 1 MeV）的P偏析的增加小于0.1的钢的单层覆盖物，其散装含量不超过0.02wt％。硬化更强烈影响DBTT偏移比那些钢的P隔离。通过中子流量增强晶界凝聚的分离C的还原对于导致DBTT转变的变化不大。

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