Recent progress in understanding reactor pressure vessel steel embrittlement
Recent progress in understanding reactor pressure vessel steel embrittlement
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DOI：
10.1080/10420159808229676
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发表时间：
1998-06
影响因子：
1
通讯作者：
G. Odette;G. Lucas
中科院分区：
文献类型：
--
作者：
G. Odette;G. Lucas
本文综述了目前对反应堆压力容器用钢辐照脆化基本机理的认识。在约290°C的操作温度下的辐射增强扩散a导致各种超细尺度硬化相的形成，包括富铜和铜催化的富锰镍沉淀物。其他不需要铜的纳米特征，即所谓的基体缺陷，包括合金磷化物和碳氮化物以及缺陷簇-溶质复合物。在辐照下热不稳定（退火）的基体缺陷在介导通量和温度效应中起着非常重要的作用。特征的平衡取决于钢的成分和辐照条件。富铜相是含有大量微量铜元素的合金的主要脆化特征，这一点已得到相当好的理解。与此相反，详细的身份和病因的基体缺陷和锰镍丰富的阶段，并没有发现。
Abstract This paper reviews the current understanding of the basic mechanisms of irradiation embrittlement in reactor pressure vessel steels. Radiation enhanced diffusiona at operating temperatures around 290°C leads to the formation of various ultrafine scale hardening phases, including copper rich and copper catalysed manganese-nickel rich precipitates. Other nanofeatures that do not require copper, so-called matrix defects, include alloy phosphides and carbonitrides as well as defect cluster-solute complexes. Matrix defects that are thermally unstable (anneal) under irradiation play a very important role in mediating flux and temperature effects. The balance of features depends on the composition of the steel and the irradiation conditions. Copper enriched phases, which are the dominant embrittling feature in alloys containing significant trace quantities of this element, are fairly well understood. In contrast, the detailed identity and etiology of the matrix defects and manganese-nickel rich phases t...