蒙特卡罗共轭输运法计算反应堆压力容器快中子注量率

为了保证压力容器（RPV）在核电厂寿期内的安全，通过理论方法准确评估其受到的快中子积分注量率非常重要。本文提出了一种应用共轭输运理论解决深穿透问题的计算方法，并将该方法的计算结果与基准题HBR-2给出的实测值及确定论方法的结果进行了比较。结果表明：本文计算结果与基准题给出的实测数据吻合良好，大多反应率计算相对误差小于10%，最大相对误差不超过35%；70%以上的计算结果准确性优于确定论方法，表明本文提出的解决蒙特卡罗深穿透问题的方法是有效且准确的。

Calculation of Reactor Pressure Vessel Fast Neutron Fluence Rate via Monte Carlo Adjoint Transport Method

In order to ensure the safety and reliability of reactor pressure vessel (RPV) during the lifetime of nuclear power plant, it is very important to theoretically evaluate the fast neutron fluence rate. In this paper, a method of calculating problem of deep penetration using the adjoint transport theory was proposed. The results of this method were compared with the HBR-2 benchmark data and the deterministic method results. The results show that the calculation results are in good agreement with the measurement results. The relative errors of reaction rates are mostly less than 10% and the maximum relative error is less than 35%. The accuracy of more than 70% of the calculated results is better than that of the deterministic method. It shows that the method proposed in this paper to solve the deep penetration of Monte Carlo is effective and accurate.