EPR堆芯严重事故下安全壳内γ辐射水平MCNP模拟与分析

γ Radiation Level Simulation and Analysis With MCNP in EPR Containment During Severe Accident

1.
School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
2.
Suzhou Nuclear Power Research Institute, Suzhou 215004, China

摘要: 根据EPR堆芯结构、材料组成及其屏蔽系统设计，建立了EPR堆芯γ辐射剂量率模拟模型。采用MCNP5分别计算了反应堆正常运行工况、堆芯失水及堆芯融化等严重事故条件下安全壳内γ剂量率空间分布，分析对比严重事故、正常工况下安全壳内辐射剂量率分布与设计剂量率限值的差异。研究结果可为预估EPR堆芯事故情况及核事故应急决策提供相关数据参考。
- EPR ,
- 严重事故 ,
- γ剂量率 ,
- MCNP5
Abstract: The γ dosimetry model based on the EPR core structure, material composition and the designed shielding system was established. The γ-ray dose rate distributions in EPR containment under different conditions including normal operation state, loss-of-coolant accident and core melt severe accident were simulated with MCNP5, and the calculation results under normal operation state and severe accident were compared and analyzed respectively with that of the designed limit. The study results may provide some relative data reference for EPR core accident prediction and reactor accident emergency decision making.
- EPR ,
- severe accident ,
- γ-ray dose rate ,
- MCNP5

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