铀加工与燃料制造设施核临界事故所致瞬发剂量计算研究

Calculation Study of Prompt Dose from Uranium Processing and Fuel Fabrication Facility in Criticality Accident

建立了基于蒙特卡罗(MCNP)程序建模的铀加工与燃料制造设施核临界事故工况下瞬发剂量的计算方法,并将该计算方法与EJ/T 988-96规定的计算方法进行了比较分析。以我国某核燃料元件研发厂址为例,采用MCNP程序建模计算了该厂址核临界事故对厂界公众所致的瞬发剂量。结果表明,EJ/T 988-96的计算方法过于保守的估计了核临界事故工况下的瞬发剂量;基于MCNP程序建模的计算方法,因其求解算法的科学性和模型对屏蔽介质的准确描述,以及结果误差的可控性,使得计算结果更准确。因此,建议采用基于MCNP程序建模的方法计算铀加工与燃料制造设施核临界事故下的瞬发剂量。

A method for calculating the prompt dose of Uranium Processing and Fuel Fabrication Facilities under nuclear criticality accidents based on MCNP code modeling was established,and the analysis and comparison was done with the calculation method stipulated in criteria EJ/T988-96.Then took a fuel research and development site at home as an example,the prompt dose of public on the edge of site was calculated.The results showed that the prompt dose in a nuclear criticality accident was overvalued using the calculation method stipulated in criteria;The modeling method based on MCNP made the calculation result more accurate because of its scientific algorithm,accurate description of shielding medium and controllability of the result error.Therefore,it is suggested that the MCNP-based code modeling method be used to assess the prompt dose under the nuclear criticality accidents of Uranium Processing and Fuel Fabrication Facilities.