普贤堆退役放射性评价方法及主蒸汽管道室的中子能谱计算  

Radioactivity Evaluation Methods for Decommissioning and Calculation of Neutron Spectrum for Main Steam Pipe Room of Fugen

作　　者：沈瑾[1] 杨洪润[1] 

机构地区：[1]中国核动力院核反应堆系统设计技术国家重点实验室,成都610041

出　　处：《核动力工程》2004年第6期555-558,共4页Nuclear Power Engineering

摘　　要：介绍了日本普贤堆(Fugen)的概况和主要设计参数,以及该堆今后的技术发展趋势。根据该堆的退役现状,介绍日本的退役战略方针以及普贤堆采用的退役方法和今后的退役步骤,并采用MCNP程序对普贤核电厂主蒸汽管道内蒸汽17N(β,n)反应产生的相对中子通量和中子能谱进行计算,据此分析了主蒸汽密度、主蒸汽管道半径对中子能谱计算结果的影响。结果表明,改变电厂运行瞬态不会影响主蒸汽管道室的中子注量分布,而增大主蒸汽管道尺寸则能够有效地降低管道保温材料所受的中子照射,这一结果对今后电厂核设施的辐照影响分析以及放射性评价具有一定的意义。The main systems and design parameters of the first prototype ATR (Advanced Thermal Reactor) Fugen of Japan are introduced in this paper. It is also shows the development of decommissioning policy in Japan and the decommissioning technology for Fugen . Based on the calculation for neutron flux distribution and neutron energy spectrum under 17N(β,n) reaction in main steam pipe room of Fugen by MCNP code and the analysis of the effect of steam density and steam pipe diameter on calculation results, it concluded that the power transient would not effect the neutron distribution in main steam pipe room and the enlargement of the diameter of steam pipe would help to reduce the radiation in cover materials on steam pipe.

关 键 词：普贤堆 退役技术 MCNP程序 蒙特卡罗计算方法 中子能谱分析 

分 类 号：TL328[核科学技术—核技术及应用] TL7