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1. 发明授权

US4569820A Nuclear reactor core and fuel element therefor 失效
标题翻译：核反应堆核心和燃料元件
公开(公告)号：US4569820A
公开(公告)日：1986-02-11
申请号：US263300
申请日：1981-05-13
申请人： Peter Fortescue
发明人： Peter Fortescue
IPC分类号： G21C3/00 , G21C15/08
CPC分类号： G21C3/00 , G21C15/08 , Y02E30/40
摘要： The present invention relates to a nuclear reactor core and fuel elements therefore. Stackable fuel elements, having the usual coolant holes machined therethrough, are formed with grooves along their vertical extent for alignment with similar grooves on adjacent fuel elements to define additional coolant passageways. These grooves provide coolant passageways between adjacent fuel elements enhancing the mechanical stability of the core. Furthermore, these additional coolant passageways allow a more efficient utilization of reactor core space and permit coolant escaping into the interstices between adjacent ends of blocks to be collected at these additional coolant passageways. Stability may be enhanced further by means of complementary elevations and depressions formed on end faces of the fuel blocks.
摘要翻译：本发明涉及核反应堆核心和燃料元件。具有通过其加工的通常的冷却剂孔的可堆叠燃料元件沿其垂直方向形成有凹槽，用于与相邻燃料元件上的相似凹槽对准以限定额外的冷却剂通道。这些凹槽在相邻的燃料元件之间提供冷却剂通道，增强了芯的机械稳定性。此外，这些额外的冷却剂通道允许更有效地利用反应堆堆芯空间并允许冷却剂逸出到在这些另外的冷却剂通道处被收集的块的相邻端之间的间隙中。通过在燃料块的端面上形成的互补的高度和凹陷可以进一步增强稳定性。

2. 发明授权

US3240678A Pressure tube neutronic reactor and coolant control means therefor 失效
标题翻译：压力管中子反应堆和冷却液控制装置
公开(公告)号：US3240678A
公开(公告)日：1966-03-15
申请号：US30382563
申请日：1963-08-22
申请人： WESTINGHOUSE ELECTRIC CORP
发明人： HEMMERLE ELMER H , SADLER JOHN W , TOWER STEPHEN N
IPC分类号： G21C1/20 , G21C15/02 , G21C15/08 , G21D5/06
CPC分类号： G21C15/08 , G21C1/20 , G21C15/02 , G21D5/06 , G21Y2002/201 , G21Y2004/302 , Y02E30/40 , Y10S376/911

3. 发明公开

EP3506318A2 PRESSURE-TUBE REACTOR WITH PRESSURISED MODERATOR 审中-公开
公开(公告)号：EP3506318A2
公开(公告)日：2019-07-03
申请号：EP19151545.1
申请日：2011-04-21
申请人： Atomic Energy of Canada Limited/ Énergie Atomique du Canada Limitée
发明人： BODNER, Robert , TYO, Jonathan , POPOV, Dan , KURAN, Sermet
IPC分类号： G21C1/10 , G21C5/02 , G21C19/19 , G21C15/02
CPC分类号： G21C1/20 , G21C1/086 , G21C1/10 , G21C5/02 , G21C15/02 , G21C15/08 , G21C15/20 , G21C19/14 , G21C19/19 , Y02E30/40
摘要： A nuclear reactor can include a pressure vessel for containing a pressurized moderator at a first pressure. The nuclear reactor can also include a plurality of fuel channels for a coolant fluid at a second pressure. The plurality of fuel channels are fluidly connected at inlet ends thereof to a coolant supply conduit and are adapted to receive nuclear fuel bundles and to be mounted within the pressure vessel and surrounded by the moderator. The outlet ends of the fuel channels are fluidly connected to a coolant outlet conduit to enable the coolant fluid to circulate from the coolant supply conduit through the fuel channels to the coolant outlet conduit. The plurality of fuel channels maintain separation between the coolant fluid circulating within the fuel channels and the moderator.

4. 发明公开

EP2561512A4 PRESSURE-TUBE REACTOR WITH PRESSURISED MODERATOR 审中-公开
标题翻译：与加压制动物质在压力管式反应器
公开(公告)号：EP2561512A4
公开(公告)日：2017-01-18
申请号：EP11771446
申请日：2011-04-21
申请人： ATOMIC ENERGY OF CANADA LTD
发明人： BODNER ROBERT , TYO JONATHAN , POPOV DAN , KURAN SERMET
IPC分类号： G21C1/10 , G21C5/02 , G21C15/02 , G21C19/19
CPC分类号： G21C1/20 , G21C1/086 , G21C1/10 , G21C5/02 , G21C15/02 , G21C15/08 , G21C15/20 , G21C19/14 , G21C19/19 , Y02E30/40
摘要： A nuclear reactor can include a pressure vessel for containing a pressurized moderator at a first pressure. The nuclear reactor can also include a plurality of fuel channels for a coolant fluid at a second pressure. The plurality of fuel channels are fluidly connected at inlet ends thereof to a coolant supply conduit and are adapted to receive nuclear fuel bundles and to be mounted within the pressure vessel and surrounded by the moderator. The outlet ends of the fuel channels are fluidly connected to a coolant outlet conduit to enable the coolant fluid to circulate from the coolant supply conduit through the fuel channels to the coolant outlet conduit. The plurality of fuel channels maintain separation between the coolant fluid circulating within the fuel channels and the moderator.

5. 发明公开

EP2561512A1 PRESSURE-TUBE REACTOR WITH PRESSURISED MODERATOR 审中-公开
标题翻译： DRUCKROHRREAKTOR MIT EINER UNTER DRUCK STEHENDEN BREMSSUBSTANZ
公开(公告)号：EP2561512A1
公开(公告)日：2013-02-27
申请号：EP11771446.9
申请日：2011-04-21
申请人： Atomic Energy of Canada Limited
发明人： BODNER, Robert , TYO, Jonathan , POPOV, Dan , KURAN, Sermet
IPC分类号： G21C1/06 , G21C1/08 , G21C19/19
CPC分类号： G21C1/20 , G21C1/086 , G21C1/10 , G21C5/02 , G21C15/02 , G21C15/08 , G21C15/20 , G21C19/14 , G21C19/19 , Y02E30/40
摘要： A nuclear reactor can include a pressure vessel for containing a pressurized moderator at a first pressure. The nuclear reactor can also include a plurality of fuel channels for a coolant fluid at a second pressure. The plurality of fuel channels are fluidly connected at inlet ends thereof to a coolant supply conduit and are adapted to receive nuclear fuel bundles and to be mounted within the pressure vessel and surrounded by the moderator. The outlet ends of the fuel channels are fluidly connected to a coolant outlet conduit to enable the coolant fluid to circulate from the coolant supply conduit through the fuel channels to the coolant outlet conduit. The plurality of fuel channels maintain separation between the coolant fluid circulating within the fuel channels and the moderator.
摘要翻译：核反应堆可以包括用于在第一压力下容纳加压调节剂的压力容器。核反应堆还可以包括用于在第二压力下的冷却剂流体的多个燃料通道。多个燃料通道在其入口端处流体连接到冷却剂供应管道并且适于接收核燃料束并且被安装在压力容器内并被调节器包围。燃料通道的出口端流体地连接到冷却剂出口导管，以使得冷却剂流体能够从冷却剂供应导管通过燃料通道循环到冷却剂出口导管。多个燃料通道保持在燃料通道和调节器之间循环的冷却剂流体之间的分离。

6. 发明申请

WO2019067819A1 PLATE TYPE NUCLEAR MICRO REACTOR 审中-公开
公开(公告)号：WO2019067819A1
公开(公告)日：2019-04-04
申请号：PCT/US2018/053270
申请日：2018-09-28
申请人： WESTINGHOUSE ELECTRIC COMPANY LLC
发明人： ARAFAT, Yasir , VAN WYK, Jurie J.
IPC分类号： G21C1/04 , G21C3/36 , G21C15/257
CPC分类号： G21C15/257 , F28D15/0233 , F28D15/0275 , F28D15/046 , F28D15/06 , F28D2021/0054 , F28F3/08 , G21C3/36 , G21C5/02 , G21C5/12 , G21C5/16 , G21C15/08 , G21C21/00 , G21D3/001
摘要： This invention provides a nuclear reactor design that can enable automated or semi-automated manufacturing of a small reactor in a mechanized factory. This is possible by following a layered approach to combine simple "plate" geometries with the use of diffusion bonding and computer aided manufacturing techniques that integrate all the fuel, axial reflectors, axial gamma and neutron shields, fuel gas plenum, heat removal mechanism, primary heat exchangers and moderator all in one block or component. The final assembled block has no welds and limits or eliminates manual operations. This design has the potential to reduce the fabrication time of an entire nuclear reactor to just a few days.

7. 发明申请

WO2017096614A1 核电站严重事故反应堆长期水源非能动pH值调节系统及方法审中-公开
公开(公告)号：WO2017096614A1
公开(公告)日：2017-06-15
申请号：PCT/CN2015/097146
申请日：2015-12-11
申请人：中广核工程有限公司 , 中国广核集团有限公司
发明人：陈兴 , 温亮
IPC分类号： G21C15/08 , G21C9/00
CPC分类号： G21C9/00 , G21C15/08 , Y02E30/40
摘要：一种核电站严重事故反应堆长期水源非能动pH值调节系统及方法，该pH值调节系统包括：安全壳（60）；设置于安全壳（60）内的反应堆压力容器（10）、碎片拦截装置（20）、回水管道（30）、侧壁设有溢流口（404）且底部设有pH值调节篮（402）的房间（40），以及与房间（40）通过溢流口（404）连通的内置换料水池（50）。在严重事故后，该pH值调节系统利用安全注入系统对反应堆注水冷却形成的水循环流动，以非能动的方式向内置换料水池内的水源添加化学药剂以调节水源的pH值，不需要外部电源或核电站中的安全级蓄电池等设备，结构简单可靠。

8. 发明公开

EP2402954A3 Pressure-loss adjusting-member installation tool 审中-公开
标题翻译：压力损失调整安装工具
公开(公告)号：EP2402954A3
公开(公告)日：2014-11-19
申请号：EP11171938.1
申请日：2011-06-29
申请人： Mitsubishi Heavy Industries, Ltd.
发明人： Matsumoto, Atsushi , Kubo, Noboru , Yoshimura, Ryo
IPC分类号： G21C19/105 , G21C3/22 , G21C5/06 , G21C15/02 , G21C15/08
CPC分类号： G21C19/105 , G21C3/22 , G21C5/06 , G21C15/02 , G21C15/08 , Y10T29/49895 , Y10T29/53 , Y10T29/531 , Y10T29/53961 , Y10T29/53983 , Y10T29/53991
摘要： A pressure-loss adjusting-member installation tool (70) to be used at a time of assembly of a reactor including: pressure-loss adjusting-member grippers (80) each of which can freely grip or release a pressure-loss adjusting member, which is arranged at a position between a lower nozzle arranged at one end of a fuel assembly having a relatively small pressure-loss when light water used as a primary coolant flows and a lower core support plate, and can cause the light water to pass therethrough in a state with a pressure-loss being increased more than that of when the light water passes through only core support plate flow holes formed on the lower core support plate; and a frame (71) that holds a number of the pressure-loss adjusting-member grippers (80) in a same positional relationship as a relative positional relationship between the fuel assemblies arranged in plural on the lower core support plate.

9. 发明公开

EP2402954A2 Pressure-loss adjusting-member installation tool 审中-公开
标题翻译： Druckverlust-Einstellglied-Installationswerkzeug
公开(公告)号：EP2402954A2
公开(公告)日：2012-01-04
申请号：EP11171938.1
申请日：2011-06-29
申请人： Mitsubishi Heavy Industries, Ltd.
发明人： Matsumoto, Atsushi , Kubo, Noboru , Yoshimura, Ryo
IPC分类号： G21C5/06 , G21C15/02 , G21C15/08
CPC分类号： G21C19/105 , G21C3/22 , G21C5/06 , G21C15/02 , G21C15/08 , Y10T29/49895 , Y10T29/53 , Y10T29/531 , Y10T29/53961 , Y10T29/53983 , Y10T29/53991
摘要： A pressure-loss adjusting-member installation tool (70) to be used at a time of assembly of a reactor including: pressure-loss adjusting-member grippers (80) each of which can freely grip or release a pressure-loss adjusting member, which is arranged at a position between a lower nozzle arranged at one end of a fuel assembly having a relatively small pressure-loss when light water used as a primary coolant flows and a lower core support plate, and can cause the light water to pass therethrough in a state with a pressure-loss being increased more than that of when the light water passes through only core support plate flow holes formed on the lower core support plate; and a frame (71) that holds a number of the pressure-loss adjusting-member grippers (80) in a same positional relationship as a relative positional relationship between the fuel assemblies arranged in plural on the lower core support plate.
摘要翻译：一种压力损失调节构件安装工具（70），其在组装反应器时使用，包括：压力损失调节构件夹持器（80），每个能够自由地夹紧或释放压力损失调节构件; 其布置在布置在具有相对较小的压力损失的燃料组件的一端处的下喷嘴之间的位置处，当用作主要冷却剂的轻水流动时，以及下部芯支撑板，并且可以使光水通过处于比仅通过形成在下芯支撑板上的芯支撑板流动孔的情况下的压力损失增加的状态。以及将多个压力损失调节构件夹持器（80）保持在与在下芯支撑板上多个排列的燃料组件之间的相对位置关系相同的位置关系的框架（71）。

10. 发明授权

US3296084A Temperature control of graphitemoderated nuclear reactors 失效
标题翻译：石墨化核反应堆的温度控制
公开(公告)号：US3296084A
公开(公告)日：1967-01-03
申请号：US42730365
申请日：1965-01-22
申请人： ATOMIC ENERGY AUTHORITY UK
发明人： SYDNEY FAWCETT , HALE BARNS , VALENTINE MOORE RICHARD , BURTON CUTTS
IPC分类号： G21C1/02 , G21C1/12 , G21C7/02 , G21C15/08
CPC分类号： G21C1/02 , G21C1/12 , G21C7/02 , G21C15/08 , G21Y2002/201 , G21Y2004/302 , Y02E30/33 , Y02E30/34 , Y02E30/39

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