核压力容器防止辐照脆化的安全评定

本文结合我国核动力反应堆的实例,首先介绍了设计规范中采用的断裂分析图的评定方法,然后着重讨论一种新的断裂力学的评定方法。结合对容器材料断裂韧性的实验测定,给出了计算结累,绘制了全寿期的安全运行工况图,并对两种方法的结果作了比较讨论。

A Safety Evaluation Method for Nuclear Pressure Vessels

The nuclear pressure vessels will be undergone the neutron irradiation in the period of operation, and for this reason the Brcttle Transition Temperature of the vessel steels will be raised and the dangers to catastrophic failure will de enlarged. In order to ensure the safety and reliability of reactors the restricted conditions of operation must be proposed according to the progress of embrittlement. Two different methods for the restrictions have been discussed in this paper. The first one which have been accepted by the ASME Design Code is the Fracture Analysis Diagram method, and the second suggested by us is the method based on fracture mechanics. The theoretical basis and the practice calculations for the second method have been presented in more details in this paper in relaton to the practical vessel designed in china.