![]() The LFFH engine described utilizes a central fusion chamber surrounded by multiple layers of multiplying and moderating media. When examining the LFFH energy mission, a significant portion of the United States and world energy production could be supplied by LFFH plants. A LFFH combines current Laser Inertial Confinement fusion technology with that of advanced fission reactor technology to produce a system that eliminates many of the negative aspects of pure fusion or pure fission systems. Muir, The NJOY nuclear data processing system, Version 91, LA-12740-M.This study investigates the neutronics design aspects of a hybrid fusion-fission energy system called the Laser Fusion-Fission Hybrid (LFFH). Parrinello, Nuclear analysis of an ITER blanket module. X-5 Monte Carlo Team, MCNP-A General Monte Carlo N-Particle Transport Code Overview and Theory (Version 5, vol. Turner, Comparison of global variance reduction techniques for Monte Carlo radiation transport simulations of ITER. Hoogenboom, An easy to implement global variance reduction procedure for MCNP. Mosher, FW-CADIS method for global and semi-global variance reduction of monte carlo radiation transport calculations. Becker, Hybrid Monte Carlo/Deterministic Methods for Deep-Penetration Problems, Doctoral Dissertation, University of Michigan (2009) Larsen, Automated weight windows for global monte carlo particle transport calculations. Peplow, Comparison of hybrid methods for global variance reduction in shielding calculations. Chen et al., Benchmarking of CAD-based SuperMC with ITER benchmark model. Habibi et al., Blanket simulation and tritium breeding ratio calculation for ITER reactor. Jiang et al., Neutronics analysis and optimization for fusion driven subcritical spent fuel burning system. Doctor’s thesis, Tsinghua University (2012) Guo, Thermal–Hydraulic Design and Coupled Analysis with Neutronics of Subcritical Energy Blanket. Huang et al., Multi-scale thermal engineering simulation on the inlet flow blockage accident of pressure tube embedded fuel component. Xie, Optimization of coolant arrangement for fusion-fission hybrid reactor and analysis of ex-core nature circulation. Jie et al., Thermal-mechanical coupling analysis of subcritical energy blanket for fusion fission hybrid reactor. Huang, Hongwen, Research development on conceptual design of subcritical blanket driven by magnetic fusion reactor. Izquierdo et al., Developments and needs in nuclear analysis of fusion technology. ![]() Loughlin et al., Nuclear analysis and shielding optimisation in support of the ITER in-vessel viewing system design. Marriott et al., Detailed 3-D nuclear analysis of ITER blanket modules. Lu et al., Tolerance analysis based on 3D models for in-wall shielding of ITER vacuum vessel. Chen et al., Shielding Analysis for ITER equatorial port cell during blanket replacement. Wu et al., Conceptual Design and Analysis of CFETR TF Coil. Arumugam, Nuclear shielding of openings in ITER Tokamak building. Chang et al., Thermal analysis on detailed 3D models of ITER thermal shield. Choi et al., Cooling optimization for preliminary design of ITER blanket shield block. Zeng, Whole structure conceptual design of subcritical blanket driven by ITER. ![]() Based on the configuration analysis, nuclear analysis and GVR method, an optimal FFHER blanket shielding design has been obtained. Neutron irradiation damage has been studied to evaluate the material damage. Power deposited and dose rate distributions have also been simulated and analysed. The spatial distribution of neutron and gamma flux have been assessed along the shield block depth. For the radiation deep-penetration problem, the flux and statistical relative error of forward MC estimate are applied to get an optimal weight window for global variance reduction (GVR). The shielding analysis is performed by Monte Carlo (MC) method. In this study, a shielding design of combining several different material shield blocks has been proposed. Therefore, it is necessary to make detail shielding design and carry out radiation analysis according to the blanket structure and material property. The hybrid of fusion core and fission blanket makes the spectra rather complex. In FFHER, shield blocks provide nuclear shielding and thermal shielding for internal and external blanket components. A preliminary design of fusion–fission hybrid energy reactor (FFHER) has been proposed by Institute of Nuclear Physics and Chemistry based on current fusion science and well-developed fission technology.
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