【摘要】 采用MCNP程序与ANISN程序结合的计算方案获取了SPRR-300反应堆混凝土屏蔽层内的中子注量率分布情况,同时采用固体核径迹探测器测量了混凝土屏蔽层外低水平中子注量率,两者吻合较好,说明了计算结果的可信性。上述结果为反应堆退役工作提供了放射性源项的计算依据。更多还原

【Abstract】 The neutron flux distribution in the concrete shielding of SPRR-300 reactor is achieved with MCNP code and ANISN code,and it is well accorded with the result of the low neutron flux outsides the concrete shielding which is gained by solid state nuclear track detector.The credibility of the calculation result is confirmed and the data is provided to calculate the radioactivity source for the retiring of the SPRR-300 reactor.更多还原