【摘要】 本文建立了退役反应堆活化源项的计算模型,通过临界计算验证了模型的正确性。介绍了对于距堆芯较远的区域采用分层计算和分步计算的重要意义,通过MCNP和ORIGEN程序相结合,计算了距堆芯较远处的支撑裙、铅支撑筒内侧和外侧钢板样品和一次水箱外筒的预留样品60 Co比活度,计算值与测量值的偏差满足退役工程设计需求,表明本文所建立的退役反应堆放射性活化源项计算方法和模型是适用的。更多还原

【Abstract】 The calculation model of radioactive activated source term for decommissioned reactor was set up,and the validity of the model was verified by critical calculation.The significance of layering calculation and stepping calculation for the area far from the reactor core was analyzed by MCNP code.Using the combination of MCNP and ORIGEN codes,the specific activities of 60Co of reactor core components,such as the reactor support skirt,the samples of the inner and outer steel plates of the lead support barrel and the pre-installed sample on the outer part of the primary water barrel,were calculated specifically.The deviation between the calculation value and measurement value meets the engineering design requirements,and this shows that the model and the calculation method for calculating the radioactive activated source term for such a decommissioned reactor are adequate.更多还原