Validity of FLUKA applied to calculation of fast neutron fluence in reactor pressure vessel
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摘要: 基于知识产权的考虑，通过与蒙特卡罗程序MCNP计算结果比对，研究使用FLUKA程序替代MCNP程序进行反应堆压力容器快中子注量计算的可行性。通过修改和调用子程序对次级粒子堆栈进行操作，解决了关闭裂变中子这一关键问题，FLUKA程序的计算结果与MCNP程序的计算结果相对偏差在5%以内，符合得较好,证明使用FLUKA程序替代MCNP程序用于计算反应堆压力容器快中子注量在技术上是可行的。Abstract: Based on the consideration of intellectual property, in order to find an alternative code of MCNP, the validity of FLUKA applied to the calculation of neutron fluence in reactor pressure vessel was studied by means of comparison of calculation results of the both codes. The secondary particle stack was manipulated by modifying and calling the user subroutines, and then the key problem of turning off the transportation of fission neutrons was solved. The results of FLUKA and MCNP code agree well with each other, with the relative deviation less than 5%. It is concluded that using FLUKA code in place of MCNP code is technically feasible.
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Key words:
- FLUKA code /
- Monte Carlo code /
- reactor pressure vessel /
- neutron fluence
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