微型反应堆乏燃料专用运输容器研制
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摘要
针对微型反应堆乏燃料运输容器设计了专门用于装载微堆乏燃料的组件。容器由屏蔽容器和吊篮组成,外部尺寸为540×831 mm,主要屏蔽材料为铅,主要结构材料为不锈钢。采用ORIGEN2计算最大源强,使用MCNP模拟计算容器表面及距离1 m处剂量率水平。屏蔽实验和实际测量结果表明,容器装载乏燃料时辐射水平小于通常的剂量约束值,也低于GB11806-2004对工作人员的剂量限值,符合微堆乏燃料安全运输的实际需求。
Miniature Neutron Source Reactor(MNSR)spent fuel transportation cask designed specifically for loading HEU core is used to ensure spent fuel transport safety in MNSR LEU conversion or decommissioning. MNSR spent fuel transportation cask consists of two parts: the shielding cask and basket. The final design of the cask size is 540×831 mm.The main structural materials are stainless steel and aluminum alloy, and the main shielding material is lead. ORIGEN2 is used for source term calculation. The dose rates of the cask surface and 1 m away from surface are calculated by MCNP.The shielding experiment and actual measurement results show that the radiation level of the shielding cask when the spent fuel is loaded is less than the usual dose constraint value. The staff radiation level is less than the staff limit dose of GB11806. The results show that MNSR transportation cask can meet the actual needs of safe transportation of miniature reactor spent fuel.
Miniature Neutron Source Reactor(MNSR)spent fuel transportation cask designed specifically for loading HEU core is used to ensure spent fuel transport safety in MNSR LEU conversion or decommissioning. MNSR spent fuel transportation cask consists of two parts: the shielding cask and basket. The final design of the cask size is 540×831 mm.The main structural materials are stainless steel and aluminum alloy, and the main shielding material is lead. ORIGEN2 is used for source term calculation. The dose rates of the cask surface and 1 m away from surface are calculated by MCNP.The shielding experiment and actual measurement results show that the radiation level of the shielding cask when the spent fuel is loaded is less than the usual dose constraint value. The staff radiation level is less than the staff limit dose of GB11806. The results show that MNSR transportation cask can meet the actual needs of safe transportation of miniature reactor spent fuel.
引文
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[11] JONAH S A,IBIKUNLEI K,LI Y.A feasibility study of LEU enrichment uranium fuels for MNSR conversion using MCNP[J].Annals of Nuclear Energy,2009,36(8):1285-1286.
[2]郝倩.微堆堆本体培训资料[Z].[出版地不详]:[出版者不详],2013.
[3]王成孝.核能与核技术应用[M].北京:原子能出版社,2002:126-129.
[4]李义国,杜开文,夏普,等.原型微堆低浓化初步研究[J].原子能科学技术,2012,46(9):403-405.
[5]熊厚华,彭旦,蔡德富,等.微型反应堆低浓化可行性初步研究[J].原子能科学技术,2008,42(9):209-211.
[6]李义国.济南微堆卸料安全分析报告[R].[出版地不详]:[出版者不详],2009.
[7]反射性物质运输安全规程:GB11806-2004[S].
[8]放射性物质安全运输条例:TS-R-1[S].
[9]郭诚湛.原型微型中子源反应堆最终安全分析报告[R].[出版地不详]:[出版者不详],1989.
[10]徐治龙,刘振宇,沈峰.济南微堆退役源项和剂量计算分析[C]//反应堆数值计算与粒子输运学术会议暨反应堆物理会议.2010.
[11] JONAH S A,IBIKUNLEI K,LI Y.A feasibility study of LEU enrichment uranium fuels for MNSR conversion using MCNP[J].Annals of Nuclear Energy,2009,36(8):1285-1286.