RADIATION EMBRITTLEMENT AND THERMAL ANNEALING BEHAVIOR OF CR-NI-MO REACTOR PRESSURE VESSEL MATERIALS

摘要

The last generation of Russian type of reactor vessels (WWER-1000) is made of low alloy chromium-nickel-molybdenum steel. In order to study the radiation behavior of that steel, fourteen different materials, i.e. eight base metals and six weld metals, have been irradiated to different fluences at 290 degrees C. The results of the corresponding Charpy V-notch impact tests are represented in this article. Some results of tensile tests are also given. Emphasis is given to the roles of metallurgical variables and dose effect. The results indicate anomalous dose dependence of irradiation-induced impact transition temperature shift. The corresponding trend curve has been proposed. Some of the irradiated materials have been subsequently annealed. It has been shown that the restoration effectiveness of anneal increases with increasing annealing temperature from 400 to 490 degrees C, and nickel enhances residual shift after postirradiation annealing at 460 degrees C. [References: 62]