A FUEL ASSEMBLY
    51.
    发明申请
    A FUEL ASSEMBLY 审中-公开

    公开(公告)号:US20190198183A1

    公开(公告)日:2019-06-27

    申请号:US16330496

    申请日:2017-02-20

    IPC分类号: G21C3/32 G21C19/307

    摘要: A fuel assembly for a nuclear water reactor having an upstream end, a downstream end, and a flow interspace between the upstream and downstream ends. Fuel rods are provided in the flow interspace between the upstream and downstream ends. The flow interspace permits a flow of coolant through the fuel assembly along a flow direction from the upstream end to the downstream end. A filter device is provided to catch debris particles in the flow of coolant. The filter device has a first filter zone for a major part of the flow of coolant, and a second filter zone for a minor part of the flow of coolant. The first filter zone has a first filtering efficiency and the second filter zone has a second filtering efficiency. The second filtering efficiency is higher than the first filtering efficiency.

    Process for the accurate characterization of low level nuclear waste

    公开(公告)号:US09779841B2

    公开(公告)日:2017-10-03

    申请号:US14186536

    申请日:2014-02-21

    摘要: A method of determining and quantifying the presence and concentration of regulated radionuclides present in filter material used to remove radionuclide contaminants from the cooling water of a nuclear reactor. Multiple samples of the reactor cooling water are taken and the presence and concentration of directly measurable fission and activation produced radionuclides are determined through gamma spectroscopy. The release rate of radioactivity from the reactor as a function of the removal rate of the filter material is determined at equilibrium. The presence and the concentration of the indirectly measured fission regulated radionuclides are determined as a function of release rates of the directly measurable fission produced isotopes.

    Apparatus and method for stripping tritium from molten salt
    59.
    发明授权
    Apparatus and method for stripping tritium from molten salt 有权
    从熔盐中剥离氚的设备和方法

    公开(公告)号:US09564251B2

    公开(公告)日:2017-02-07

    申请号:US14333627

    申请日:2014-07-17

    申请人: UT-Battelle, LLC

    摘要: A method of stripping tritium from flowing stream of molten salt includes providing a tritium-separating membrane structure having a porous support, a nanoporous structural metal-ion diffusion barrier layer, and a gas-tight, nonporous palladium-bearing separative layer, directing the flowing stream of molten salt into contact with the palladium-bearing layer so that tritium contained within the molten salt is transported through the tritium-separating membrane structure, and contacting a sweep gas with the porous support for collecting the tritium.

    摘要翻译: 从熔融盐流中提取氚的方法包括提供具有多孔载体的氚分离膜结构,纳米多孔结构金属离子扩散阻挡层和气密的无孔钯载体分离层,引导流动 熔融盐流与含钯层接触,使得熔融盐中所含的氚通过氚分离膜结构输送,并将吹扫气与多孔载体接触以收集氚。

    MECHANICAL COMPONENT
    60.
    发明申请
    MECHANICAL COMPONENT 审中-公开
    机械部件

    公开(公告)号:US20160111175A1

    公开(公告)日:2016-04-21

    申请号:US14868934

    申请日:2015-09-29

    申请人: ROLLS-ROYCE PLC

    发明人: Claire ALLISON

    IPC分类号: G21C19/307 G21C1/02

    摘要: This disclosure concerns reducing or elimination the build-up of coolant materials in the fuel handling and component maintenance systems of nuclear reactors, thereby reducing or eliminating manual cleaning of said components. A mechanical component (2) for use within the handling route of the reactor is provided with drainage channels (8) to disperse coolant material deposited on the component. A heater (4) may also be employed to avoid the build-up.

    摘要翻译: 本公开涉及减少或消除在核反应堆的燃料处理和部件维护系统中的冷却剂材料的积聚,从而减少或消除对所述部件的手动清洁。 在反应器的处理路径内使用的机械部件(2)设置有排放通道(8),以分散沉积在部件上的冷却剂材料。 还可以使用加热器(4)来避免积聚。