-
公开(公告)号：US11742099B2
公开(公告)日：2023-08-29
申请号：US16888766
申请日：2020-05-31
Applicant: GE-Hitachi Nuclear Energy Americas LLC
Inventor： Brian S. Hunt , Christer N. Dahlgren , Wayne Marquino
IPC: G21C13/036 , G21C9/004 , G21C1/08 , G21C1/02 , G21C15/18 , G21C13/02 , G21C9/016 , G21C9/033 , G21C17/04 , G21C13/093 , G21C13/087
CPC classification number: G21C9/004 , G21C1/028 , G21C1/086 , G21C9/016 , G21C13/02 , G21C15/18 , G21C9/033 , G21C13/087 , G21C13/093 , G21C17/042
Abstract: Nuclear reactors have very few systems for significantly reduced failure possibilities. Nuclear reactors may be boiling water reactors with natural circulation-enabling heights and smaller, flexible energy outputs in the 0-350 megawatt-electric range. Reactors are fully surrounded by an impermeable, high-pressure containment. No coolant pools, heat sinks, active pumps, or other emergency fluid sources may be present inside containment; emergency cooling, like isolation condenser systems, are outside containment. Isolation valves integral with the reactor pressure vessel provide working and emergency fluid through containment to the reactor. Isolation valves are one-piece, welded, or otherwise integral with reactors and fluid conduits having ASME-compliance to eliminate risk of shear failure. Containment may be completely underground and seismically insulated to minimize footprint and above-ground target area.
-
2.发明授权Apparatus for controlling coolant level in a liquid-metal-cooled nuclear reactor 失效用于控制液态金属冷却核反应堆中的冷却水平的装置
公开(公告)号：US4113562A
公开(公告)日：1978-09-12
申请号：US789154
申请日：1977-04-20
Applicant: Robert D. Jones
Inventor： Robert D. Jones
IPC: G21C1/02 , G21C17/035
CPC classification number: G21C17/035 , G21C1/028 , Y02E30/34
Abstract: A liquid-metal-cooled fast-breeder reactor which has a thermal liner spaced inwardly of the pressure vessel and includes means for passing bypass coolant through the annulus between the thermal liner and the pressure vessel to insulate the pressure vessel from hot outlet coolant includes control ports in the thermal liner a short distance below the normal operating coolant level in the reactor and an overflow nozzle in the pressure vessel below the control ports connected to an overflow line including a portion at an elevation such that overflow coolant flow is established when the coolant level in the reactor is above the top of the coolant ports. When no makeup coolant is added, bypass flow is inwardly through the control ports and there is no overflow; when makeup coolant is being added, coolant flow through the overflow line will maintain the coolant level.
-
公开(公告)号：US3703437A
公开(公告)日：1972-11-21
申请号：US87079869
申请日：1969-08-20
Applicant: GULF OIL CORP
Inventor： FORTESCUE PETER , SHANSTROM RAYMOND T
CPC classification number: G21C1/322 , G21C1/02 , G21C1/022 , G21C1/028 , G21C3/32 , G21C9/00 , G21C9/001 , G21C11/08 , Y02E30/34
Abstract: ZONTAL GRID STRUCTURE. THE TUBES ARE SECURED IN THE GRID STRUCTURE AND MATE THEREWITH AT THEIR UPPER ENDS.
A NUCLEAR POWDER FAST REACTOR SYSTEM IS DESCRIBED WHICH UTILIZES GAS AS A COOLANT. THE REACTOR SYSTEM INCLUDES A PRESTRESSED CONCRETE CONTAINMENT VESSEL WHICH CONTAINS THE ENTIRE PRIMARY SYSTEM OF THE REACTOR, COMPRISING THE CORE, CONTROL ROD DRIVE MECHANISMS, COOLANT CIRCULATORS, STEAM GENERATORS AND ASSOCIATED MAIN COOLANT DUCTING. THE INTERIOR OF THE VESSEL IS SEPARATED INTO TWO REGIONS, THE LOWER ONE CONTAINING THE CORE AND HAVING PROVISION FOR EXPLOSION ABSORPTION AND WATER FLOODING. THE CORE IS COMPRISED OF FUEL ELEMENTS SUPPORTED IN A PLURALITY OF ELONGRATED TUBES WHICH DEPEND FREELY FROM A GENERALLY HORI--
公开(公告)号：US3275521A
公开(公告)日：1966-09-27
申请号：US32400863
申请日：1963-11-15
Applicant: BABCOCK & WILCOX CO
Inventor： SCHLUDERBERG DONALD C , WINDERS GORDON R
-
5.发明申请STEAM GENERATOR FOR SODIUM COOLED FAST REACTOR, HEAT TRANSFER TUBES THEREOF, AND LEAK DETECTION UNIT FOR HEAT TRANSFER TUBE THEREOF 有权用于冷却的快速反应器的蒸汽发生器，其传热管及其传热管的泄漏检测单元公开(公告)号：US20100064988A1
公开(公告)日：2010-03-18
申请号：US12413416
申请日：2009-03-27
Applicant: Ho-Yun NAM , Byoung-Hae CHOI , Byung-Ho KIM , Jong-Man KIM
Inventor： Ho-Yun NAM , Byoung-Hae CHOI , Byung-Ho KIM , Jong-Man KIM
CPC classification number: F16L9/18 , F22B1/066 , G21C1/028 , G21C17/002 , G21D1/006 , Y02E30/40 , Y10T137/0452
Abstract: A steam generator, used in a helical coil type steam generator for a sodium-cooled fast reactor which has heat transfer tubes of a double-wall tube structure, with high heat transfer efficiency and a heat transfer tube damage detection unit that can detect on-line in real-time whether the heat transfer tube is damaged or not. The heat transfer tube of a steam generator for a sodium-cooled fast reactor, includes an inner tube formed with a first material; an outer tube formed with a second material that is in close contact with the inner tube and which has a thermal expansion coefficient less than that of the first material; and a plurality of helium flow grooves formed between the inner tube and the outer tube along a lengthwise direction of the heat transfer tube for flowing helium gas. The inner tube and the outer tube are identically due to heat for the temperature difference generated during normal operation of the steam generator, so the degree of close contact between the inner tube and the outer tube does not decrease, and the decrease of heat transfer efficiency can be prevented.
Abstract translation: 一种蒸汽发生器，用于具有双壁管结构的传热管，具有高传热效率的传热管和热传导管损坏检测单元的用于钠冷快速反应器的螺旋线圈式蒸汽发生器， 实时传输管道是否损坏。 用于钠冷快堆的蒸汽发生器的传热管包括形成有第一材料的内管; 形成有与内管紧密接触的第二材料并且其热膨胀系数小于第一材料的热膨胀系数的外管; 以及沿着用于流动氦气的传热管的长度方向在内管和外管之间形成的多个氦流动槽。 内管和外管同样由于蒸汽发生器正常运行时产生的温度差而产生的热量，因此内管和外管之间的紧密接触程度不会降低，传热效率降低 可以防止。
-
Patent Agency Ranking
公开(公告)号：US3929566A
公开(公告)日：1975-12-30
申请号：US37304973
申请日：1973-06-25
Applicant: COMBUSTION ENG
Inventor： NOYES RICHARD CROISSANT
Abstract: A plurality of volume displacing modules removably positioned in the peripheral space between a liquid metal cooled reactor vessel and the walls of the containment structure forming a vessel cavity in which the vessel is disposed to insure that the level of coolant in the reactor vessel remains above a predetermined elevation in the event of coolant leakage into the vessel cavity. The reactor vessel is provided with an excess volume of liquid metal coolant. The total volume of the modules positioned in the peripheral space below the predetermined elevation is such that the coolant containing volume in the peripheral space with the modules in place is less than the volume of excess liquid metal coolant in the reactor.
Abstract translation: 多个容积移动模块可移除地定位在液体金属冷却的反应器容器和容纳结构的壁之间的周边空间中，形成容器空腔，容器设置在容器腔中，以确保反应容器中的冷却剂的水平保持在 在冷却剂泄漏到容器腔中的情况下的预定高度。 反应器容器设有过量的液态金属冷却剂。 位于外围空间中位于预定高度以下的模块的总体积使得具有模块就位的外围空间中的冷却剂容积小于反应器中多余的液态金属冷却剂的体积。
-
公开(公告)号：US3414473A
公开(公告)日：1968-12-03
申请号：US58351966
申请日：1966-10-03
Applicant: BABCOCK & WILCOX CO
Inventor： SCHLUDERBERG DONALD C , WINDERS GORDON R , DOSSETT JOHN S
-
-
公开(公告)号：US3345266A
公开(公告)日：1967-10-03
申请号：US52474866
申请日：1966-02-03
Applicant: ATOMIC ENERGY AUTHORITY UK
Inventor： ERSKINE MANN JOHN , ALLAN BARKER , ARTHUR PERKS MAURICE
-
公开(公告)号：US20240312650A1
公开(公告)日：2024-09-19
申请号：US18228635
申请日：2023-07-31
Applicant: GE-Hitachi Nuclear Energy Americas LLC
Inventor： Brian S. Hunt , Christer N. Dahlgren , Wayne Marquino
IPC: G21C9/004 , G21C1/02 , G21C1/08 , G21C9/016 , G21C9/033 , G21C13/02 , G21C13/087 , G21C13/093 , G21C15/18 , G21C17/04
CPC classification number: G21C9/004 , G21C1/028 , G21C1/086 , G21C9/016 , G21C13/02 , G21C15/18 , G21C9/033 , G21C13/087 , G21C13/093 , G21C17/042
Abstract: Nuclear reactors have very few systems for significantly reduced failure possibilities. Nuclear reactors may be boiling water reactors with natural circulation-enabling heights and smaller, flexible energy outputs in the 0-350 megawatt-electric range. Reactors are fully surrounded by an impermeable, high-pressure containment. No coolant pools, heat sinks, active pumps, or other emergency fluid sources may be present inside containment; emergency cooling, like isolation condenser systems, are outside containment. Isolation valves integral with the reactor pressure vessel provide working and emergency fluid through containment to the reactor. Isolation valves are one-piece, welded, or otherwise integral with reactors and fluid conduits having ASME-compliance to eliminate risk of shear failure. Containment may be completely underground and seismically insulated to minimize footprint and above-ground target area.
-
-
-
-
-
-
-
-
-
Search Results
28
records
(took 0.008 seconds)
