Transport and Burnup Numerical Simulation on the Liquid Blanket Burnup of In-Zinerater

SHI Xueming; YANG Junyun; LIU Cheng'an

doi:10.11804/NuclPhysRev.31.02.248

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Article Navigation > Nuclear Physics Review > 2014 > 31(2): 248-252

SHI Xueming, YANG Junyun, LIU Cheng'an. Transport and Burnup Numerical Simulation on the Liquid Blanket Burnup of In-Zinerater[J]. Nuclear Physics Review, 2014, 31(2): 248-252. doi: 10.11804/NuclPhysRev.31.02.248

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SHI Xueming, YANG Junyun, LIU Cheng'an. Transport and Burnup Numerical Simulation on the Liquid Blanket Burnup of In-Zinerater[J]. Nuclear Physics Review, 2014, 31(2): 248-252. doi: 10.11804/NuclPhysRev.31.02.248

Transport and Burnup Numerical Simulation on the Liquid Blanket Burnup of In-Zinerater

doi: 10.11804/NuclPhysRev.31.02.248

Institute of Applied Physics and Computational Mathematics, Beijing 100088, China;

Received Date: 1900-01-01
Rev Recd Date: 1900-01-01
Publish Date: 2014-06-20

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.
- Z-Pinch inertial confinement fusion,
- fission,
- transuranic element,
- transmutation
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通讯作者: 陈斌, bchen63@163.com

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沈阳化工大学材料科学与工程学院沈阳 110142

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Transport and Burnup Numerical Simulation on the Liquid Blanket Burnup of In-Zinerater

doi: 10.11804/NuclPhysRev.31.02.248

Institute of Applied Physics and Computational Mathematics, Beijing 100088, China;

Received Date: 1900-01-01
Rev Recd Date: 1900-01-01
Publish Date: 2014-06-20

Key words:

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.

Citation: