Grain-boundary phosphorus segregation in highly neutron-irradiated reactor pressure vessel steels and its effect on irradiation embrittlement
Grain-boundary phosphorus segregation in highly neutron-irradiated reactor pressure vessel steels and its effect on irradiation embrittlement
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强中子辐照反应堆压力容器钢的晶界磷偏析及其对辐照脆化的影响
DOI：
10.1016/j.jnucmat.2020.152564
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发表时间：
2021
影响因子：
3.1
通讯作者：
Nagai Yasuyoshi
中科院分区：
文献类型：
--
作者：
Hata Kuniki;Takamizawa Hisashi;Hojo Tomohiro;Ebihara Kenichi;Nishiyama Yutaka;Nagai Yasuyoshi
用于压水堆（PWR）的反应堆压力容器（RPV）钢，其本体磷含量范围为0.007至0.012wt.%，在压水堆或材料测试反应堆（MTR）中以0.3至1.2 × 1020n/cm2（E> 1 MeV）的注量进行中子辐照。使用俄歇电子能谱 (AES) 对晶间面进行分析，发现晶界 P 偏析随着中子注量的增加而增加。基于替代磷原子、八面体间隙磷原子、空位和自间隙原子的四个扩散反应方程的速率理论模型也被用来模拟体积磷含量高达 0.020wt.% 的 RPV 钢晶界磷偏析的增加，并使用由现有 AES 数据优化的参数。散装磷含量为 0.015wt.% 的 RPV 钢中晶界磷偏析的增加（这是拟重启的日本核电站使用的 RPV 钢中磷的最大浓度）在 1 × 1020n/cm2（E> 1 MeV）下的单层覆盖率估计小于 0.1。 PWR 数据与 MTR 数据（包括文献中的数据）的比较表明，中子通量对 A533B 钢的晶界 P 偏析没有影响。还讨论了韧脆转变温度（DBTT）变化与晶界磷偏析和屈服强度的关系。对于大量磷含量高达 0.026wt.% 的 RPV 钢，屈服强度与 DBTT 偏移之间呈线性关系，斜率为 0.63，高于大多数美国 A533B 钢。结论是，压水堆辐照后的 RPV 钢不太可能发生晶间脆化。
Reactor pressure vessel (RPV) steels for pressurized water reactors (PWRs) with bulk P contents ranging from 0.007 to 0.012wt.% were subjected to neutron irradiation at fluences ranging from 0.3 to 1.2 × 1020n/cm2(E> 1 MeV) in PWRs or a materials testing reactor (MTR). Grain-boundary P segregation, which was analyzed using Auger electron spectroscopy (AES) on intergranular facets, increased with increasing neutron fluence. A rate theory model based on four diffusion-reaction equations for substitutional P atoms, octahedral interstitial P atoms, vacancies, and self-interstitial atoms was also used to simulate the increase in grain-boundary P segregation for RPV steels with a bulk P content up to 0.020wt.%, using parameters optimized by the present AES data. The increase in grain-boundary P segregation in RPV steel with a bulk P content of 0.015wt.%, which is the maximum P concentration in RPV steels used in Japanese nuclear power plants intended for restart, was estimated to be less than 0.1 in monolayer coverage at 1 × 1020n/cm2(E> 1 MeV). A comparison of the PWR data with the MTR data, including that from the literature, showed that neutron flux had no effect upon grain-boundary P segregation for A533B steels. The relationships of the ductile-brittle transition temperature (DBTT) shifts to grain-boundary P segregation and to yield strength were also discussed. A linear relationship between the yield strength and the DBTT shift with a slope of 0.63 was obtained for RPV steels with a bulk P content up to 0.026wt.%, which is higher than that of most U.S. A533B steels. It is concluded that the intergranular embrittlement is unlikely to occur for RPV steels irradiated in PWRs.
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