DORT程序进行RPV中子注量率计算的可靠性验证

Reliability validation of RPV neutron flux calculated by DORT

反应堆压力容器(RPV)中的碳钢材料受到快中子辐照会发生性能变化。为了防止由于RPV的材料性能发生变化而不适当地限制核电厂的运行,需要限定核电厂寿期内RPV中的最大快中子注量,并且要求安装辐照监督管对RPV材料所受到的快中子注量进行监督。因此,RPV和辐照监督管中子注量率的精确计算对RPV的辐照安全和寿命管理具有十分重要的意义。三代非能动压水堆核电厂主要采用基于BUGLE-96截面库的二维离散纵标法程序DORT进行RPV中子注量率计算。本文利用秦山核电厂第五根辐照监督管的中子注量率测量数据和MCNP-4B计算结果与DORT程序的计算结果进行比较,来验证采用DORT程序进行RPV母材段中子注量率计算的可靠性。

The fracture toughness property of ferritic material in the reactor pressure vessel（RPV） will change due to fast neutron irradiation.In order to prevent restricting the operation of nuclear power plant impropriety because of the property change of material,the fast neutron fluence in RPV during the life of nuclear power plant must be restricted,and the radiation surveillance capsules are need to be installed to monitor the fast neutron fluence in RPV.So the calculation accuracy of the neutron flux in RPV and the radiation surveillance capsules is very important to radiation safety and life management of RPV.In GEN-III nuclear power plant.2D S_N program DORT based on BUGLE-96 is mainly adopted in RPV neutron flux calculation.The purpose of this paper is to validate the reliability of neutron flux in RPV base metal calculated by DORT using the measured values and the calculation results by MCNP-4B of neutron flux about the fifth radiation surveillance capsule in Qinshan nuclear power plant.