反应堆压力容器寿命的概率评估
Probabilistic assessment of the reactor vessel lifetime
AI总结：
提出一种基于含时生死随机过程与排队论的快速概率方法，用于评估中子辐照导致的反应堆压力容器钢壁寿命缩短，并明确所需参数及数据获取难点。
摘要：
本文提出了一种简单而快速的方法，用于评估中子辐照下反应堆压力容器钢壁寿命的缩短。该方法基于通过一般的含时生死随机过程的行为和排队论来对辐射缺陷数量进行建模。评估所需的数据包括：反应堆的预计运行时间（以年计）、反应堆的实际运行时间、随时间变化的累积注量、反应堆压力容器壁的温度、反应堆壁钢材的中子吸收截面，以及撞击壁面的快中子能量。主要问题在于获取这些准确数据。
英文摘要：
A simple and rapid method is proposed for assessing the reduction in the lifetime of steel walls of the reactor vessel under neutron irradiation. The method is based on modeling the number of radiation defects by the behavior of a general time-dependent random process of death and birth and queuing theory. Necessary data for assessments: the estimated operating time of the reactor (in years), the actual operating time of the reactor, the accumulated fluence depending on time, the temperature on the walls of the reactor vessel, the neutron absorption cross section of the steel of the reactor walls, the energy of fast neutrons striking the walls. The main problem: getting this accurate data.
机构、总结、中文摘要均由AI分析而来，可能存在错误，请以论文正文为准。
