CAJ | 학술논문

Z-Pinch惯性约束聚变是未来一种有竞争力的能源候选方案。Z-Pinch驱动的聚变裂变混合堆可高效地嬗变反应堆乏燃料中分离出的超铀元素。对美国Sandia国家实验室提出的In-Zinerater混合堆概念进行了中子学分析和数值模拟。在三维输运燃耗耦合程序MCORGS中增加了处理在线添加燃料与去除裂变产物的功能，实现了对液态燃料燃耗过程的模拟。增加6Li丰度和燃料初装量保持寿期初反应性不变，可以减缓寿期内反应性下降趋势。逐步增加包层内超铀元素装量，可以控制整个寿期内反应性基本恒定。聚变功率取20 MW，通过反应性控制，5年内包层能量放大倍数在160～180之间，氚增殖比在1.5～1.7之间，优于In-Zinerater基准设计方案。
Z-Pinch관성약속취변시미래일충유경쟁력적능원후선방안。Z-Pinch구동적취변렬변혼합퇴가고효지선변반응퇴핍연료중분리출적초유원소。대미국Sandia국가실험실제출적In-Zinerater혼합퇴개념진행료중자학분석화수치모의。재삼유수운연모우합정서MCORGS중증가료처리재선첨가연료여거제렬변산물적공능，실현료대액태연료연모과정적모의。증가6Li봉도화연료초장량보지수기초반응성불변，가이감완수기내반응성하강추세。축보증가포층내초유원소장량，가이공제정개수기내반응성기본항정。취변공솔취20 MW，통과반응성공제，5년내포층능량방대배수재160～180지간，천증식비재1.5～1.7지간，우우In-Zinerater기준설계방안。
Z-Pinch Inertial confinement fusion is a competitive candidate for future energy solution. A fusion-fission hybrid driven by Z-Pinch can be used to transmute transuranic elements from spent fuels of reactors efficiently. Analysis and numerical simulation of blanket neutronics of In-Zinerater, which is a fusion-fission hybrid concept design in Sandia National Laboratories, is given in this paper. Modification to the three dimension transport and burnup code MCORGS are done, so as to simulate continuous feeding and continuous chemical processing of the liquid fuel. Different combination of initial enrichment of 6Li and fuels loading in the blanket are selected to keep the same reactivity at begin of core. By this way, the decreasing trend of reactivity at life of the core can be lowered. The reactivity can be maintained constant by increasing the fuel loading in the core gradually as the burnup deepens. Given a 20 MW fusion power, by reactivity control, the blanket energy multiplication is around 160～180 and tritium breed ratio 1.5～1.7 in 5 years, which is a better result than Sandia’s original design.