基于蒙特卡罗方法的新型乏燃料干式贮存容器辐射安全仿真验证

发布时间：2018-12-31 20:29

【摘要】：针对自主设计的贮存24组燃耗深度为45 GWD/MTU的乏燃料组件的CHN-24型专用容器临界及辐射屏蔽问题,采用蒙特卡罗程序MCNP,建立CHN-24容器临界及辐射屏蔽计算模型。研究结果表明:正常贮存条件下容器内乏燃料的有效增殖因数(k_(eff))为0.283,发生浸水事故时,k_(eff)随着容器内水位升高逐渐增大,注满水时keff达到最大值0.706;容器表面剂量当量率随浸水量增大而减小;正常贮存条件下,即无水浸入时,容器表面及距表面1 m处的最大剂量当量率值分别为0.42 m Sv·h~(-1)、0.08 m Sv·h~(-1)。以上均符合国际原子能机构规定的临界及剂量安全标准,同时表明蒙特卡罗方法可应用于乏燃料容器的临界及辐射屏蔽安全验证。该研究为我国研发具有自主知识产权的核电乏燃料贮存专用容器提供了一定的参考依据。
[Abstract]:Aiming at the critical and radiation shielding problem of the CHN-24 type special vessel designed for storing 24 groups of spent fuel assemblies with burnup depth of 45 GWD/MTU, Monte Carlo program MCNP, was used to establish the calculation model of critical and radiation shielding for CHN-24 vessels. The results show that under normal storage conditions, the effective multiplication factor of spent fuel (k _ (eff) = 0.283) increases with the increase of water level. The maximum value of keff was 0.706 when filled with water; The surface dose equivalent rate of the vessel decreases with the increase of water immersion. Under normal storage conditions, I. e., the maximum dose equivalent rates of 0. 42 m Sv h ~ (-1) and 0. 08 m Sv h ~ (-1) of the vessel surface and 1 m from the surface of the vessel are respectively 0. 42 m / h ~ (-1) and 0. 08 m Sv / h ~ (-1). All of the above are in accordance with the critical and dose safety standards set by the International Atomic Energy Agency. It is also shown that the Monte Carlo method can be used to verify the criticality and radiation shielding safety of spent fuel vessels. The research provides a reference for the development of nuclear spent fuel storage containers with independent intellectual property rights.
【作者单位】：南京航空航天大学核科学与工程系;江苏省核能装备材料工程实验室;
【基金】：江苏省产学研联合创新资金项目(No.BY2014003-04) 南京航空航天大学研究生创新基地开放基金(No.kfjj20150602) 江苏高校优势学科建设工程项目资助~~
【分类号】：TM623.8

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