-
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
CPC分类号: G21C3/3206 , G21C3/3305 , G21C19/307 , Y02E30/40
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.
-
公开(公告)号:US20180268949A1
公开(公告)日:2018-09-20
申请号:US15923491
申请日:2018-03-16
发明人: ARTEM ALESHIN , DAVID S. HUEGEL , WILLIAM CLEARY
IPC分类号: G21C3/32 , G21C19/307
CPC分类号: G21C3/3206 , G21C3/3305 , G21C19/307 , Y02E30/40
摘要: A base portion for use in a bottom nozzle of a fuel assembly in a nuclear reactor includes a top surface, a bottom surface, and a plurality of vertical wall portions arranged in a generally squared grid-like pattern which extend between the bottom surface and the top surface and which define a plurality of non-circular passages passing between the bottom surface and the top surface through the base portion.
-
53.
公开(公告)号:US20180264458A1
公开(公告)日:2018-09-20
申请号:US15984711
申请日:2018-05-21
申请人: EBARA CORPORATION
发明人: Takeshi IZUMI , Makoto KOMATSU
IPC分类号: B01J47/028 , B01J47/026 , B01J47/04 , C02F1/42 , C02F1/70 , G21C19/307 , G21F9/12 , B01J41/05 , C02F101/00 , C02F101/10 , C02F103/02 , C02F103/04
CPC分类号: B01J47/028 , B01J41/05 , B01J47/026 , B01J47/04 , C02F1/42 , C02F1/705 , C02F2001/422 , C02F2001/425 , C02F2001/427 , C02F2101/006 , C02F2101/10 , C02F2103/023 , C02F2103/04 , G21C19/307 , G21F9/12
摘要: A purification method for spent fuel pool water from nuclear power generation, the method comprising: passing the water at a linear flow velocity of 50 m/h or less through a purification apparatus for the water comprising an ion exchange resin layer and a metal-doped resin layer which is laid at a bed height of 2 cm or more on a surface layer of the ion exchange resin layer wherein the water to be treated is contacted with the metal-doped resin layer to decompose a pro-oxidant contained in the water; and subsequently contacting the water with the ion exchange resin.
-
公开(公告)号:US09999880B2
公开(公告)日:2018-06-19
申请号:US14520635
申请日:2014-10-22
申请人: EBARA CORPORATION
发明人: Takeshi Izumi , Makoto Komatsu
IPC分类号: G21F9/12 , B01J47/028 , B01J47/04 , C02F1/42 , C02F1/70 , G21C19/307 , B01J47/026 , B01J41/05 , C02F101/00 , C02F101/10 , C02F103/02 , C02F103/04
CPC分类号: B01J47/028 , B01J41/05 , B01J47/026 , B01J47/04 , C02F1/42 , C02F1/705 , C02F2001/422 , C02F2001/425 , C02F2001/427 , C02F2101/006 , C02F2101/10 , C02F2103/023 , C02F2103/04 , G21C19/307 , G21F9/12
摘要: A method for purifying water in a spent fuel pool in a nuclear power plant, the method including passing the water at a linear flow velocity of 50 m/h or less through a purification apparatus. The apparatus includes an ion exchange resin layer and a metal-doped resin layer laid at a bed height of 2 cm or more on a surface layer of the ion exchange resin layer. The method includes contacting the water with the metal-doped resin layer to decompose a pro-oxidant contained in the water and subsequently contacting the water with the ion exchange resin to produce purified water.
-
公开(公告)号:US09850581B2
公开(公告)日:2017-12-26
申请号:US15048227
申请日:2016-02-19
发明人: Akio Sayano , Norihisa Saito , Tetsuji Kaneko , Yasuo Morishima , Masato Okamura , Kenji Yamazaki , Kunihiko Kinugasa
IPC分类号: C23C30/00 , C23C18/12 , C23C26/00 , F04F5/10 , F04F5/46 , G21C15/25 , G21C19/307 , G21C1/08 , G21C17/022
CPC分类号: C23C30/005 , C23C18/1216 , C23C18/1241 , C23C26/00 , F04F5/10 , F04F5/46 , G21C1/084 , G21C15/25 , G21C17/0225 , G21C19/307 , Y02E30/31
摘要: A coating of niobium oxide, zirconium titanate, or nickel titanate is formed on at least a part of a surface of a jet pump member constituting a jet pump serving as a reactor internal structure of a boiling water reactor. Further, a solution containing, e.g., a niobium compound is applied to at least a part of the surface of the jet pump member constituting the jet pump, and the jet pump member coated with the solution is heat-treated to form a coating of, e.g., niobium oxide. With this configuration, the jet pump member constituting the jet pump of the boiling water reactor is provided such that deposition of crud can be sufficiently suppressed on the jet pump member.
-
56.
公开(公告)号:US20170345519A1
公开(公告)日:2017-11-30
申请号:US15637621
申请日:2017-06-29
IPC分类号: G21C19/28 , G21F9/00 , G21C19/307 , G21F9/30 , G21C17/022
CPC分类号: G21C19/28 , G21C17/0225 , G21C19/307 , G21F9/004 , G21F9/30
摘要: This invention generally concerns radioactive decontamination of deposits on components in a nuclear power plant and is specifically concerned with improved systems and methods for disrupting, dissolving, removing and reducing at ambient temperature radionuclides formed on the primary side surfaces of components in a pressurized water reactor and the internal components of a boiling water reactor. The methods include identifying the structure, taking the structure out of operational service, contacting the structure with an aqueous solution (e.g., a recirculating flow or static immersion), and adding an effective amount of elemental metal in solid form to the aqueous solution.
-
公开(公告)号:US09779841B2
公开(公告)日:2017-10-03
申请号:US14186536
申请日:2014-02-21
申请人: David W James , Tom Kalinowski
发明人: David W James , Tom Kalinowski
IPC分类号: G21C17/022 , G21C17/00 , G21F9/12 , G21C19/307
CPC分类号: G21C17/002 , G21C17/022 , G21C19/307 , G21F9/12
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.
-
58.
公开(公告)号:US20170176315A1
公开(公告)日:2017-06-22
申请号:US15375346
申请日:2016-12-12
CPC分类号: G01N15/0806 , G01N2015/084 , G21C15/182 , G21C17/022 , G21C19/307 , Y02E30/40
摘要: Acquiring sets of test data on amounts of foreign matter passed through a recirculation sump screen when different amounts of foreign matter are input; forming a passed foreign matter amount approximate line that approximates the amounts of passed foreign matter with respect to the amounts of input foreign matter on the basis of the sets of test data on the amounts of passed foreign matter; forming a passed foreign matter amount envelope tangent to the passed foreign matter amount approximate line; and estimating a total passed foreign matter amount with respect to the amounts of input foreign matter on the basis of the passed foreign matter amount envelope to evaluate the recirculation sump screen are provided.
-
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
发明人: David E. Holcomb , Dane F. Wilson
IPC分类号: G21C19/31 , G21G1/00 , G21C19/307 , G21F9/06 , G21C3/54
CPC分类号: G21C19/307 , G21C3/54 , G21C15/28 , G21F9/06 , G21F9/12 , G21G1/001 , G21G2001/0094
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。
-
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
CPC分类号: G21C19/307 , G21C1/02 , G21C1/03 , G21C19/02 , G21C19/20
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。
-
-
-
-
-
-
-
-
-