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REACTOR DESIGN WITH CONTROLLED THERMAL NEUTRON FLUX FOR ENHANCED NEUTRON ACTIVATION POTENTIAL
REACTOR DESIGN WITH CONTROLLED THERMAL NEUTRON FLUX FOR ENHANCED NEUTRON ACTIVATION POTENTIAL
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机译:具有控制热中子通量的反应器设计,用于增强中子激活电位
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摘要
Reactor core and thermal neutron fission reactor has fuel rods with a composite fuel composition (each having the same uniform cross-section along their axial length), end plates at first and second ends, and intermediate support plates located along a longitudinal length of the reactor core. In a radial cross-section, the fuel rods are arranged at nodes of a hexagonal pitch arrangement, in which the nodes are in a spaced-apart arrangement and interconnected by ligaments. Openings between the nodes form part of a coolant flow path through the thermal neutron reactor core. At least two of the nodes of the hexagonal pitch arrangement are sized to allow insertion, translation, removal, or a combination thereof of auxiliary equipment, such as a target delivery system (TDS) for isotopes. Thermal neutron flux (neutrons ≤ 0.06 eV) is maximized for maximum neutron activation potential, which is applied to produce both commercial and research isotopes.
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