In-Zinerater 液态包层输运燃耗数值模拟
Transport and Burnup Numerical Simulation on the Liquid Blanket Burnup of In-Zinerater
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摘要: 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-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 fusionfission 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.Abstract: 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 fusionfission 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.
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