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1. 发明授权

US09865365B2 Decay heat removal system with hybrid heat pipe having coolant and neutron absorber for cooling nuclear power plant 有权
公开(公告)号：US09865365B2
公开(公告)日：2018-01-09
申请号：US14335324
申请日：2014-07-18
申请人： UNIST Academy-Industry Research Corporation
发明人： In Cheol Bang , Ji Hyun Kim , Seong Dae Park , Sarah Kang , Han Seo , Kyoung-Mo Kim , Sung Bo Moon , Seok Bin Seo , In Guk Kim , Yeong Shin Jeong , Hyo Heo
IPC分类号： G21C15/18 , G21C7/12 , G21C15/26 , G21C19/08 , G21C7/103 , G21C19/07
CPC分类号： G21C15/18 , G21C7/103 , G21C7/12 , G21C15/26 , G21C19/07 , G21C19/08 , Y02E30/39
摘要： Disclosed is a decay heat removal system for cooling the decay heat of a reactor core and the spent fuel. The decay heat removal system including: a first heat pipe which is placed in an upper plenum of the reactor vessel and arranged in upward and downward directions corresponding to a position of an insertion hole formed on a top of the nuclear fuel assemblies; a control rod drive mechanism which is connected to an upper portion of the first heat pipe and drives the first heat pipe to move up and down so that the first heat pipe can be selectively inserted in a control rod insertion hole of the reactor core arranged in the nuclear reactor vessel; and a second heat pipe which is coupled to and in close contact with a bottom surface of the reactor vessel and removes the decay heat generated in the reactor core.

2. 发明申请

US20110110477A1 Systems and methods for controlling reactivity in a nuclear fission reactor 有权
公开(公告)号：US20110110477A1
公开(公告)日：2011-05-12
申请号：US12590447
申请日：2009-11-06
申请人： Charles E. Ahlfeld , Ehud Greenspan , Roderick A. Hyde , Nathan P. Myhrvold , Joshua C. Walter , Kevan D. Weaver , Thomas Allan Weaver , Lowell L. Wood, JR. , George B. Zimmerman
发明人： Charles E. Ahlfeld , Ehud Greenspan , Roderick A. Hyde , Nathan P. Myhrvold , Joshua C. Walter , Kevan D. Weaver , Thomas Allan Weaver , Lowell L. Wood, JR. , George B. Zimmerman
IPC分类号： G21C7/30 , G21C17/035 , G21C3/32
CPC分类号： G21C7/08 , G21C1/026 , G21C7/06 , G21C7/103 , G21C7/30 , G21C17/035 , Y02E30/34 , Y02E30/39
摘要： Illustrative embodiments provide a reactivity control assembly for a nuclear fission reactor, a reactivity control system for a nuclear fission reactor having a fast neutron spectrum, a nuclear fission traveling wave reactor having a fast neutron spectrum, a method of controlling reactivity in a nuclear fission reactor having a fast neutron spectrum, methods of operating a nuclear fission traveling wave reactor having a fast neutron spectrum, a system for controlling reactivity in a nuclear fission reactor having a fast neutron spectrum, a method of determining an application of a controllably movable rod, a system for determining an application of a controllably movable rod, and a computer program product for determining an application of a controllably movable rod.

3. 发明申请

US20100322369A1 LIQUID COOLED NUCLEAR REACTOR WITH ANNULAR STEAM GENERATOR 审中-公开
标题翻译：液体冷却核反应堆与蒸汽发生器
公开(公告)号：US20100322369A1
公开(公告)日：2010-12-23
申请号：US12764163
申请日：2010-04-21
申请人： Yohei NISHIGUCHI
发明人： Yohei NISHIGUCHI
IPC分类号： G21C15/00
CPC分类号： G21C1/322 , G21C1/02 , G21C1/32 , G21C3/02 , G21C5/00 , G21C7/04 , G21C7/103 , Y02E30/34 , Y02E30/35 , Y02E30/39
摘要： A nuclear reactor in which a primary coolant is contained, the primary coolant moves upwardly from the core by an operation thereof. An annular steam generator is arranged in an upper side of the core into which the upwardly moving primary coolant flows and transfers heat in the primary coolant into water therein to generate a steam. A passage structure defines a coolant passage for the primary coolant to an outside of the core. The heat-transferred primary coolant in the annular steam generator flows downwardly in the coolant passage so as to flow into the core, thereby moving upwardly. A reactor vessel is arranged to surround the coolant passage so as to contain the core, the annular steam generator and the passage means therein.
摘要翻译：其中容纳有主要冷却剂的核反应堆，主冷却剂通过其操作从芯向上移动。环形蒸汽发生器布置在芯的上侧，向上移动的一次冷却剂向其中流动，并将主冷却剂中的热量转移到其中以产生蒸汽。通道结构将用于主冷却剂的冷却剂通道定义到芯的外部。环形蒸汽发生器中传热的主要冷却剂在冷却剂通道中向下流动，以便流入核心，从而向上移动。反应堆容器布置成围绕冷却剂通道以便容纳核心，环形蒸汽发生器和其中的通道装置。

4. 发明申请

US20090034674A1 NUCLEAR REACTOR CONTROL ROD 审中-公开
标题翻译：核反应堆控制炉
公开(公告)号：US20090034674A1
公开(公告)日：2009-02-05
申请号：US11830173
申请日：2007-07-30
申请人： Joseph M. Burger , George P. Smith, JR.
发明人： Joseph M. Burger , George P. Smith, JR.
IPC分类号： G21C7/10
CPC分类号： G21C7/10 , G21C7/103 , G21C7/117 , Y02E30/39
摘要： A control rod for nuclear reactor having a lower section that contains an annular neutron absorber wrapped in a metal sleeve. The sleeve rests on a lower spacer which is seated on the control rod lower end cap. The upper portion of the sleeve extends above the annular neutron absorber of this lower section and is capped by an upper spacer. The standard neutron absorber is supported above this upper spacer which rests on the upper end of the metal sleeve to define a gap between the upper spacer and the annular neutron absorber to accommodate axial expansion.
摘要翻译：一种用于核反应堆的控制棒，其具有包含环形中子吸收器的下部，该环形中子吸收器包裹在金属套筒中。套筒位于控制杆下端盖上的下垫片上。套筒的上部在该下部的环形中子吸收体的上方延伸，并被上部间隔物覆盖。标准中子吸收器被支撑在该上间隔件上方，该上间隔件位于金属套筒的上端，以限定上间隔件和环形中子吸收体之间的间隙以适应轴向膨胀。

5. 发明授权

US6088420A Reactor core 失效
标题翻译：反应堆核心
公开(公告)号：US6088420A
公开(公告)日：2000-07-11
申请号：US70909
申请日：1998-05-04
申请人： Tsugio Yokoyama , Ritsuo Yoshioka , Yasushi Tsuboi
发明人： Tsugio Yokoyama , Ritsuo Yoshioka , Yasushi Tsuboi
IPC分类号： G21C5/00 , G21C1/00 , G21C3/07 , G21C3/30 , G21C3/324 , G21C3/326 , G21C3/328 , G21C5/18 , G21C7/00 , G21C7/103 , G21C3/32 , G21C3/34
CPC分类号： G21C1/00 , G21C3/326 , G21C5/18 , G21C7/103 , G21Y2002/201 , G21Y2002/304 , G21Y2002/50 , G21Y2004/101 , G21Y2004/30 , Y02E30/31 , Y02E30/32 , Y02E30/38 , Y02E30/39
摘要： In a reactor core, there is charged a number of fuel assemblies composed of a channel box and a fuel bundle disposed therein, in which fuel rods adjacent to each other are arranged so as to provide a triangular shape and a ratio of a coolant channel cross section to a fuel cross section is set to be 1 or less.
摘要翻译：在反应堆堆芯中，装有多个由通道箱和设置在其中的燃料束组成的燃料组件，其中彼此相邻的燃料棒被布置成提供三角形状，并且冷却剂通道交叉将燃料截面的截面设定为1以下。

6. 发明授权

US5064607A Hybrid nuclear reactor grey rod to obtain required reactivity worth 失效
标题翻译：混合核反应堆灰色获得所需的反应活性
公开(公告)号：US5064607A
公开(公告)日：1991-11-12
申请号：US377492
申请日：1989-07-10
申请人： John V. Miller , William R. Carlson , Michael B. Yarbrough
发明人： John V. Miller , William R. Carlson , Michael B. Yarbrough
IPC分类号： G21C7/117 , G21C7/00 , G21C7/103 , G21C7/24
CPC分类号： G21C7/103 , G21C7/00 , G21Y2002/206 , G21Y2002/30 , G21Y2004/30 , G21Y2004/305 , Y02E30/39
摘要： Hybrid nuclear reactor grey rods are described, wherein geometric combinations of relatively weak neutron absorber materials such as stainless steel, zirconium or INCONEL, and relatively strong neutron absorber materials, such as hafnium, silver-indium cadmium and boron carbide, are used to obtain the reactivity worths required to reach zero boron change load follow. One embodiment includes a grey rod which has combinations of weak and strong neutron absorber pellets in a stainless steel cladding. The respective pellets can be of differing heights. A second embodiment includes a grey rod with a relatively thick stainless steel cladding receiving relatively strong neutron absorber pellets only. A third embodiment includes annular relatively weak netron absorber pellets with a smaller diameter pellet of relatively strong absorber material contained within the aperture of each relatively weak absorber pellet. The fourth embodiment includes pellets made of a homogeneous alloy of hafnium and a relatively weak absorber material, with the percentage of hafnium chosen to obtain the desired reactivity worth.

7. 发明授权

US4941158A Nuclear reactivity control configuration 失效
标题翻译：核反应控制配置
公开(公告)号：US4941158A
公开(公告)日：1990-07-10
申请号：US330410
申请日：1989-03-30
申请人： Billy E. Bingham , Richard V. DeMars
发明人： Billy E. Bingham , Richard V. DeMars
IPC分类号： G21C7/10 , G21C7/103 , G21C7/11 , G21C7/113
CPC分类号： G21C7/103 , G21C7/113 , G21Y2002/201 , G21Y2004/10 , G21Y2004/30 , G21Y2004/40 , Y02E30/39
摘要： A neutron flux control component for a nuclear reactor. Thin, overlapping segments of highly neutron absorbing material are positioned in the core of a reactor. The self-shielding overlapping segments are moved relative to each other to vary the amount of exposed surface area of poison to control core reactivity and to provide power shaping within the reactor core. The poison segments are mounted to carriers in the form of close-fitting concentric cylinders or rods of V-shaped cross section.
摘要翻译：核反应堆的中子通量控制组件。高中子吸收材料的薄的，重叠的段被定位在反应器的核心中。自屏蔽重叠区段相对于彼此移动以改变暴露的毒物表面积的量以控制核心反应性并且在反应堆堆芯内提供功率整形。毒物段以紧密的同心圆柱体或V形横截面的棒的形式安装到载体上。

8. 发明授权

US3959072A Compactable control element assembly for a nuclear reactor 失效
标题翻译：用于核反应堆的可压缩控制元件组件
公开(公告)号：US3959072A
公开(公告)日：1976-05-25
申请号：US401483
申请日：1973-09-27
申请人： Clive Frederick George Dupen
发明人： Clive Frederick George Dupen
IPC分类号： G21C7/103 , G21C7/08
CPC分类号： G21C7/103 , G21Y2002/104 , G21Y2004/30 , Y02E30/34 , Y02E30/39
摘要： A compactable control element assembly for a nuclear reactor in which the absorber pins of the assembly are compacted during downward movement of the pin and are returned to their uncompacted state when downward movement is stopped. The control element assembly comprises a support member longitudinally movable within a control assembly duct and a pluraity of absorber pins supported laterally outward of the support member and within the duct by pairs of support arms. The absorber pins are pivotably mounted to the support arms and the support arms in turn are supported from the support member for upward pivotable movement in a longitudinal plane. As the support member is moved downward, the support arms pivot upwardly and the absorber pins move upwardly and inwardly towards the support member. When the support member is stopped the absorber pins return to their uncompacted position.
摘要翻译：一种用于核反应堆的可压缩控制元件组件，其中组件的吸收器销在销的向下运动期间被压实并且当向下运动停止时返回到其未压缩状态。控制元件组件包括可在控制组件管道内纵向移动的支撑构件，以及通过成对的支撑臂在支撑构件横向向外支撑并且在管道内支撑的缓冲器销。吸收器销可枢转地安装到支撑臂上，并且支撑臂依次由支撑构件支撑，以在纵向平面中向上枢转运动。当支撑构件向下移动时，支撑臂向上枢转并且吸收器销向支撑构件向上和向内移动。当支撑构件停止时，吸收器销返回到其未压缩位置。

9. 发明授权

US3912582A Hydraulic balancing of a control component within a nuclear reactor 失效
标题翻译：核反应堆内控制组件的液压平衡
公开(公告)号：US3912582A
公开(公告)日：1975-10-14
申请号：US49814774
申请日：1974-08-16
申请人： US ENERGY
发明人： MARINOS DANNY , RIPFEL HANS C F
IPC分类号： G21C5/06 , G21C7/103 , G21C7/10
CPC分类号： G21C7/103 , G21C5/06 , G21Y2002/303 , G21Y2002/50 , G21Y2004/302 , Y02E30/39
摘要： A reactor control component includes an inner conduit, for instance containing neutron absorber elements, adapted for longitudinal movement within an outer guide duct. A transverse partition partially encloses one end of the conduit and meets a transverse wall within the guide duct when the conduit is fully inserted into the reactor core. A tube piece extends from the transverse partition and is coaxially aligned to be received within a tubular receptacle which extends from the transverse wall. The tube piece and receptacle cooperate in engagement to restrict the flow and pressure of coolant beneath the transverse partition and thereby minimize upward forces tending to expel the inner conduit.
摘要翻译：反应器控制部件包括内导管，例如包含中子吸收器元件，适于在外引导管内纵向移动。当导管完全插入反应堆芯中时，横向隔板部分地包围管道的一端并且与导管内的横向壁相遇。管件从横向隔板延伸并同轴对齐以容纳在从横向壁延伸的管状容器内。管件和容器配合配合以限制横向隔板下方的冷却剂的流动和压力，从而最小化倾向于排出内部导管的向上的力。

10. 发明授权

US09852818B2 Systems and methods for controlling reactivity in a nuclear fission reactor 有权
公开(公告)号：US09852818B2
公开(公告)日：2017-12-26
申请号：US12657734
申请日：2010-01-25
申请人： Charles E. Ahlfeld , Ehud Greenspan , Roderick A. Hyde , Nathan P. Myhrvold , Joshua C. Walter , Kevan D. Weaver , Thomas Allan Weaver , Lowell L. Wood, Jr. , George B. Zimmerman
发明人： Charles E. Ahlfeld , Ehud Greenspan , Roderick A. Hyde , Nathan P. Myhrvold , Joshua C. Walter , Kevan D. Weaver , Thomas Allan Weaver , Lowell L. Wood, Jr. , George B. Zimmerman
IPC分类号： G21C7/30 , G21C7/08 , G21C7/103 , G21C17/035
CPC分类号： G21C7/30 , G21C7/08 , G21C7/103 , G21C17/035 , Y02E30/34 , Y02E30/39
摘要： Illustrative embodiments provide a reactivity control assembly for a nuclear fission reactor, a reactivity control system for a nuclear fission reactor having a fast neutron spectrum, a nuclear fission traveling wave reactor having a fast neutron spectrum, a method of controlling reactivity in a nuclear fission reactor having a fast neutron spectrum, methods of operating a nuclear fission traveling wave reactor having a fast neutron spectrum, a system for controlling reactivity in a nuclear fission reactor having a fast neutron spectrum, a method of determining an application of a controllably movable rod, a system for determining an application of a controllably movable rod, and a computer program product for determining an application of a controllably movable rod.

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