公开(公告)号：US06658078B2

公开(公告)日：2003-12-02

申请号：US10066744

申请日：2002-02-06

Applicant: Takafumi Anegawa ,  Shin Takizawa ,  Shinya Mizokami

Inventor： Takafumi Anegawa ,  Shin Takizawa ,  Shinya Mizokami

IPC: G21C700

CPC classification number: G21C3/326 ,  G21Y2002/201 ,  G21Y2002/304 ,  G21Y2004/10 ,  G21Y2004/30 ,  Y02E30/38

Abstract: A MOX nuclear fuel assembly employable either for a thermal neutron reactor employing UO2 as the nuclear fuel and light water as the moderator/coolant or for a thermal neutron reactor employing the MOX fuels as the nuclear fuel and light water as the moderator/coolant is provided with only one kind of MOX nuclear fuel rods each of which has relatively large magnitude of the enrichment grade of the fissionable Pu-s or Pu239 and Pu241, the quantity of the MOX nuclear fuel rods being relatively small.

Abstract translation: MOX核燃料组件可用于使用UO2作为核燃料的热中子反应器，以及作为缓和剂/冷却剂的轻水或使用MOX燃料作为核燃料的热中子反应器和提供作为缓和剂/冷却剂的轻水 只有一种MOX核燃料棒，其中可分解的Pu-s或Pu <239>和Pu <241>的浓缩级别的量级相对较大，MOX核燃料棒的数量相对较小。

公开(公告)号：US06526115B2

公开(公告)日：2003-02-25

申请号：US09903854

申请日：2001-07-13

Applicant: Kazuyoshi Kataoka ,  Masahiro Ookawa ,  Eiko Fueki

Inventor： Kazuyoshi Kataoka ,  Masahiro Ookawa ,  Eiko Fueki

IPC: G21C1500

CPC classification number: G21C1/082 ,  G21Y2002/201 ,  G21Y2002/301 ,  G21Y2004/30 ,  Y02E30/40

Abstract: A supercritical pressure water cooled reactor comprising: a reactor vessel including: a shell part for containing sub-critical pressure coolant, and an end part for containing supercritical-pressure coolant which is separated from the sub-critical pressure coolant in the reactor vessel. A core-support plate with through-holes, the core-support plate disposed-in and fixed to the reactor vessel so that the core-support plate divides space inside the reactor vessel into a supercritical-pressure portion and a sub-critical pressure portion. Fuel tubes with both open ends fixed to the through-holes, the open ends being communicated to the supercritical-pressure portion, outside of the fuel tubes being disposed in the sub-critical pressure portion; and nuclear fuel assemblies disposed in the fuel tubes.

Abstract translation: 一种超临界压力水冷却反应器，包括：反应堆容器，其包括：用于容纳次临界压力冷却剂的壳体部分和用于容纳与反应堆容器中的次临界压力冷却剂分离的超临界压力冷却剂的端部。 具有通孔的芯支撑板，芯支撑板设置并固定到反应器容器，使得芯支撑板将反应器容器内的空间分成超临界压力部分和次临界压力部分 。 燃料管的两个开口端都固定在通孔上，开口端连接到超临界压力部分，燃料管外部设置在次临界压力部分; 以及设置在燃料管中的核燃料组件。

公开(公告)号：US20030026380A1

公开(公告)日：2003-02-06

申请号：US10066744

申请日：2002-02-06

Applicant: TOKYO ELECTRIC POWER CO.

Inventor： Takafumi Anegawa ,  Shin Takizawa ,  Shinya Mizokami

IPC: G21C003/32

CPC classification number: G21C3/326 ,  G21Y2002/201 ,  G21Y2002/304 ,  G21Y2004/10 ,  G21Y2004/30 ,  Y02E30/38

Abstract: A MOX nuclear fuel assembly employable either for a thermal neutron reactor employing UO2 as the nuclear fuel and light water as the moderator/coolant or for a thermal neutron reactor employing the MOX fuels as the nuclear fuel and light water as the moderator/coolant is provided with only one kind of MOX nuclear fuel rods each of which has relatively large magnitude of the enrichment grade of the fissionable Pu-s or Pu239 and Pu241, the quantity of the MOX nuclear fuel rods being relatively small.

Abstract translation: MOX核燃料组件可用于使用UO2作为核燃料的热中子反应器，以及作为缓和剂/冷却剂的轻水或使用MOX燃料作为核燃料的热中子反应器和提供作为缓和剂/冷却剂的轻水 只有一种MOX核燃料棒，其中可分解的Pu-s或Pu239和Pu241的浓缩级别的量级相对较大，MOX核燃料棒的数量相对较小。

公开(公告)号：US06493413B1

公开(公告)日：2002-12-10

申请号：US09604567

申请日：2000-06-27

Applicant: Thomas A. Galioto ,  Patrick M. O'Leary ,  Edward J. Ruzauskas ,  Thomas E. Vincent ,  Jerome B. Lee ,  Richard G. McClelland

Inventor： Thomas A. Galioto ,  Patrick M. O'Leary ,  Edward J. Ruzauskas ,  Thomas E. Vincent ,  Jerome B. Lee ,  Richard G. McClelland

IPC: G21C1707

CPC classification number: G21C17/04 ,  G21Y2002/201 ,  G21Y2002/304 ,  G21Y2004/30

Abstract: A fuel assembly mechanical flow restriction apparatus for detecting failure in situ of nuclear fuel rods in a fuel assembly during reactor shutdown.

公开(公告)号：US20020181644A1

公开(公告)日：2002-12-05

申请号：US10118926

申请日：2002-04-10

Applicant: General Electric Company

Inventor： Samson Hettiarachchi ,  Robert J. Law ,  David P. Siegwarth ,  Thomas P. Diaz ,  Robert L. Cowan

IPC: G21C009/00

CPC classification number: G21C19/307 ,  C23F11/18 ,  G21Y2002/103 ,  G21Y2002/201 ,  G21Y2004/20 ,  G21Y2004/40

Abstract: Method for controlling the amount of metal atoms deposited into an oxide layer present on a metal surface, which metal atoms increase the corrosion resistance of metal when present in the oxide film, wherein the metal surface is submerged in water at a selected temperature within the range of about to 200null to 550null F.; and a solution of a compound containing the metal which increases the corrosion resistance of the metal surface when present in the oxide film is injected into the water. The compound decomposes at the selected temperature to release atoms of the metal which incorporate in the oxide film at a desired loading

Abstract translation: 用于控制沉积在金属表面上的氧化物层中的金属原子的量的方法，该金属原子在存在于氧化物膜中时增加了金属的耐腐蚀性，其中金属表面在选定温度范围内浸没在水中 约为200°至550°F。 并且当存在于氧化物膜中时，含有金属的化合物溶液，其将金属表面的耐腐蚀性提高到水中。 该化合物在所选择的温度下分解以释放掺入氧化物膜中的金属原子以所需的载量

公开(公告)号：US20020163990A1

公开(公告)日：2002-11-07

申请号：US10014619

申请日：2001-12-10

Applicant: Electric Power Research Institute, Inc.

Inventor： Paul L. Frattini ,  Robert Douglas Varrin ,  Edwin Stephen Hunt

IPC: G21C019/42

CPC classification number: G21C19/32 ,  B08B3/12 ,  G21C17/06 ,  G21F9/001 ,  G21Y2002/104 ,  G21Y2002/201 ,  G21Y2002/202 ,  G21Y2002/205 ,  G21Y2002/304 ,  G21Y2002/40 ,  G21Y2004/30 ,  G21Y2004/40 ,  G21Y2004/50

Abstract: An apparatus for cleaning an irradiated nuclear fuel assembly includes a housing adapted to engage a nuclear fuel assembly. A set of ultrasonic transducers is positioned on the housing to supply radially emanating omnidirectional ultrasonic energy to remove deposits from the nuclear fuel assembly.

公开(公告)号：US06476317B1

公开(公告)日：2002-11-05

申请号：US09390898

申请日：1999-09-07

Applicant: Arthur R. Frederickson ,  Stanley Woolf ,  John C. Garth

Inventor： Arthur R. Frederickson ,  Stanley Woolf ,  John C. Garth

IPC: H05K900

CPC classification number: G21F1/12 ,  G21F1/10 ,  G21Y2002/201 ,  G21Y2002/301 ,  G21Y2004/30 ,  G21Y2004/40

Abstract: The invention provides improved shielding from high energy radiation, especially radiation in the form of electrons with kinetic energy from 0.1 to 10 million electron volts. The improvement is produced by the build-up of an electric field in the insulating material which acts to further attenuate or deflect the penetration of such radiation. The electric field builds up in the insulator and surrounding media because of the stopping of charge stemming from prior impinging radiation.

Abstract translation: 本发明提供了对来自高能量辐射的改进的屏蔽，特别是具有0.1-10万电子伏特的动能的电子形式的辐射。 通过在绝缘材料中积聚电场产生改进，其作用是进一步衰减或偏转这种辐射的穿透。 由于先前的入射辐射引起的电荷停止，电场在绝缘体和周围介质中形成。

公开(公告)号：US06456681B1

公开(公告)日：2002-09-24

申请号：US09386142

申请日：1999-08-31

Applicant: Yasushi Goto ,  Nobuaki Oono ,  Yuki Narawa ,  Teruji Tarumi ,  Koji Hirukawa

Inventor： Yasushi Goto ,  Nobuaki Oono ,  Yuki Narawa ,  Teruji Tarumi ,  Koji Hirukawa

IPC: C21C17108

CPC classification number: G21C17/108 ,  G21Y2002/201 ,  G21Y2002/301 ,  G21Y2004/30 ,  G21Y2004/305 ,  G21Y2004/40

Abstract: A neutron flux measuring apparatus, adapted to a boiling-water reactor (BWR) of a nuclear power plant and an advanced boiling-water reactor (ABWR) of a nuclear power plant, for measuring a neutron flux in a reactor pressure vessel, comprises a neutron flux detector assembly incorporating a local power range monitor detector assembly and a start-up range neutron monitor detector, a preamplifier amplifying a detector signal obtained from said start-up range neutron monitor detector, a start-up range neutron monitor operation unit operating, indicating and monitoring the amplified signal of the start-up range neutron monitor detector, and a local power range monitor operation unit operating, indicating and monitoring a signal obtained from the local power range monitor detector.

Abstract translation: 适用于核电厂的沸水反应堆（BWR）和用于测量反应堆压力容器中的中子通量的核电站的先进沸水反应堆（ABWR）的中子流量测量装置包括： 中子通量检测器组件，其包括局部功率范围监视器检测器组件和启动范围中子监视器检测器，放大从所述启动范围中子监视器检测器获得的检测器信号的前置放大器，启动范围中子监视器操作单元， 指示和监视启动范围中子监视器检测器的放大信号;以及本地功率范围监视器操作单元，其操作，指示和监视从本地功率范围监视器检测器获得的信号。

公开(公告)号：US20020080908A1

公开(公告)日：2002-06-27

申请号：US09978308

申请日：2001-10-17

Inventor： Mikihide Nakamaru ,  Hideaki Heki ,  Takehiko Saito ,  Kouji Hiraiwa ,  Tadashi Narabayashi ,  Satoru Oomizu ,  Tsuyoshi Shimoda ,  Kenji Arai ,  Shinichi Morooka ,  Seijiro Suzuki

IPC: G21C001/04

CPC classification number: G21C5/00 ,  G21C1/084 ,  G21C7/04 ,  G21C7/113 ,  G21Y2002/201 ,  G21Y2002/304 ,  G21Y2002/40 ,  G21Y2004/30 ,  Y02E30/31 ,  Y02E30/39

Abstract: The present invention is to provide a reactor core that allows a nuclear plant to continuously operate for a long term period, for example 15 years or longer, without requiring any fuel exchange, reduces the duration and number of maintenance steps involved in regular plant inspections, markedly improves plant availability and economic efficiency, and is effective in terms of nuclear nonproliferation. A plurality of fuel assemblies 103, themselves obtained by arranging fuel rods 100 and water rods 107 in square lattices, are arranged in a square lattice at a certain pitch. The blades 102a of a cross-shaped (cruciform) control rod 102 in a cross section are inserted into four adjacent spaces formed by four fuel assemblies 100 facing each other. A value of 0.06 cm31 1 or greater is selected for the ratio (B/S) of the width (B) of each blade on the cruciform control rod 102 and the surface (S) of the fuel lattice defined by the surface area of a square whose side is equal to the pitch between the fuel assemblies 103.

Abstract translation: 本发明提供一种反应堆堆芯，其允许核电厂连续运行长达15年或更长的时间，而不需要任何燃料更换，减少常规工厂检查所涉及的维护步骤的持续时间和数量， 显着提高了植物的可利用性和经济效益，在核不扩散方面有效。 通过将燃料棒100和水杆107排列成方形格子而获得的多个燃料组件103以一定的间距排列成方格。 横截面的十字形（十字形）控制杆102的叶片102a插入由彼此面对的四个燃料组件100形成的四个相邻的空间中。 对于十字形控制杆102上的每个叶片的宽度（B）和由表面积的表面积所限定的燃料晶格的表面（S）的比率（B / S），选择0.06cm31 1或更大的值 其侧面等于燃料组件103之间的间距。

公开(公告)号：US06393087B1

公开(公告)日：2002-05-21

申请号：US09439713

申请日：1999-11-12

Applicant: Dong-Seok Oh ,  Tae-Hyun Chun ,  Wang-Kee In ,  Kee-Nam Song ,  Hyung-Kyu Kim ,  Heung-Seok Kang ,  Kyung-Ho Yoon ,  Youn-Ho Jung

Inventor： Dong-Seok Oh ,  Tae-Hyun Chun ,  Wang-Kee In ,  Kee-Nam Song ,  Hyung-Kyu Kim ,  Heung-Seok Kang ,  Kyung-Ho Yoon ,  Youn-Ho Jung

IPC: G21C334

CPC classification number: G21C3/322 ,  G21C3/344 ,  G21C3/3566 ,  G21Y2002/201 ,  G21Y2002/303 ,  G21Y2004/30 ,  Y02E30/38

Abstract: A duct-type spacer grid for nuclear fuel assemblies is disclosed. In this spacer grid, a plurality of duct-shaped grid elements, individually having an octagonal cell, are closely arranged in parallel and are welded together, thus forming a matrix structure. The grid elements do not pass across the center of the subchannel of the assembly, thus effectively reducing pressure loss. Each of the grid elements is formed as an independent cell, and so they effectively resist against a lateral impact. A plurality of integral type swirl flow vanes, having different heights or same height, axially extend from the top of the grid to be positioned within each subchannel. The swirl flow vanes are bent outwardly, and so they do not contact the fuel rods during an insertion of the fuel rods into the cells. In the spacer grid, the fuel rods are supported within the cells by line contact springs without using any dimple. The spacer grid thus uniformly distributes its spring force on the fuel rods and almost completely prevents damage of the fuel rods due to fretting wear.

Abstract translation: 公开了一种用于核燃料组件的导管型间隔栅格。 在这种间隔栅格中，多个具有八边形单元格的管状栅格元件被平行地紧密排列并且被焊接在一起，从而形成矩阵结构。 网格元件不会穿过组件的子通道的中心，从而有效地减少压力损失。 每个栅格元件形成为独立的单元，因此它们有效抵抗横向冲击。 具有不同高度或相同高度的多个整体式涡流流动叶片从网格的顶部轴向延伸以定位在每个子通道内。 涡流流动叶片向外弯曲，因此在将燃料棒插入单元中时它们不接触燃料棒。 在间隔网格中，燃料棒通过线接触弹簧支撑在电池内，而不使用任何凹坑。 间隔栅格因此将其弹簧力均匀地分布在燃料棒上，并几乎完全防止由于微动磨损导致燃料棒的损坏。