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    FUEL ELEMENT WITH A SHORTENED SUPPORTING COOLANT PIPE
    281.
    发明申请
    FUEL ELEMENT WITH A SHORTENED SUPPORTING COOLANT PIPE 审中-公开
    燃料元件与缩短支冷却管

    公开(公告)号：WO1995008826A1

    公开(公告)日：1995-03-30

    申请号：PCT/DE1994001046

    申请日：1994-09-13

    Applicant: SIEMENS AKTIENGESELLSCHAFT ,  MEIER, Werner

    Inventor： SIEMENS AKTIENGESELLSCHAFT

    IPC: G21C03/322

    CPC classification number: G21C3/322 ,  G21C2003/3225 ,  G21Y2002/201 ,  G21Y2002/207 ,  G21Y2004/302 ,  Y02E30/38

    Abstract: In a boiling-water fuel element with a central coolant pipe (WR) as the backbone of the bearing frame, upper end section (WE) of the coolant pipe (WR) becomes a relatively slim linking stud (4) engaging through an aperture in the upper rod holder (1) and secured there. Thus the upper end section (WE) lies at the upper edge of the active zone (AZ) and the coolant outlets of the coolant pipe (WR) take the form of passages (8) which are axial or run inwards to the linking stud. This provides good flow conditions, especially low pressure losses, in the upper part of the fuel element.

    Abstract translation: 与中央冷却剂配管（WR）作为支持骨架的主链中的沸水燃料组件是在一个相对细长的销（4），其通过上杆保持器的开口啮合其上端（WE）的冷却剂管（WR）（1） 并附着在那里。 上端（WE）位于有源区（AZ）和冷却剂配管（WR）的冷却剂出口的上边缘是轴向或向内朝向（8）形成在所述插件定位销通道的通道。 这将创造有利的流动条件下，特别是压力损失小，达到了燃料组件的顶部。

    FUEL-BUNDLE INVERSION FOR DUAL-PHASE NUCLEAR REACTORS
    282.
    发明申请
    FUEL-BUNDLE INVERSION FOR DUAL-PHASE NUCLEAR REACTORS 审中-公开
    双相核反应堆的燃料组合逆变器

    公开(公告)号：WO1992001299A1

    公开(公告)日：1992-01-23

    申请号：PCT/US1991004644

    申请日：1991-06-28

    Applicant: GENERAL ELECTRIC COMPANY

    Inventor： GENERAL ELECTRIC COMPANY ,  CONGDON, Steven, Paul ,  FAWCETT, Russell, Morgan

    IPC: G21C19/00

    CPC classification number: G21C19/205 ,  G21C1/084 ,  G21C1/28 ,  G21C5/02 ,  G21C15/24 ,  G21C15/243 ,  G21Y2002/201 ,  G21Y2002/601 ,  G21Y2004/40 ,  Y02E30/31

    Abstract: Fuel bundles of a boiling-water nuclear reactor are inverted during refueling methods. Bundles burned in a first orientation are subjected to greater burnup near their bottoms and greater conversion of fertile fuel to fissile fuel near their tops. Inverting the bundles promotes burnup of the actinide products from the conversion of the last cycle. Thus, the procedure greater energy production efficiency and reduced actinide radioactive waste are achieved. Once inverted fuel bundles can be removed for disposal. Alternatively, they can be reinverted to burnup actinide fissile fuel generated at the bottom (while it was downstream of the top) during the second operating cycle. Further inversions are provided for, but the major gains occur during the first and second inversions.

    Abstract translation: 在加油方法中，沸水核反应堆的燃料束反转。 以第一方向燃烧的束在其底部附近受到更大的燃耗，并且在其顶部附近将可燃燃料转化为易裂变燃料。 反转束可以促进锕系元素的燃耗从上一个循环的转换。 因此，程序实现了更大的能源生产效率和降低的锕系元素放射性废物。 一旦倒置的燃料束可以被去除处置。 或者，它们可以在第二个操作循环期间被重新转换为在底部产生的燃料锕系裂变燃料（而在顶部的下游）。 提供进一步的反转，但主要收益发生在第一次和第二次反转。

    REACTIVITY CONTROL SYSTEM AND METHOD
    284.
    发明申请
    REACTIVITY CONTROL SYSTEM AND METHOD 审中-公开
    反应控制系统及方法

    公开(公告)号：WO1992001296A1

    公开(公告)日：1992-01-23

    申请号：PCT/US1991004642

    申请日：1991-06-28

    Applicant: GENERAL ELECTRIC COMPANY

    Inventor： GENERAL ELECTRIC COMPANY ,  DILLMANN, Charles, Warner

    IPC: G21C09/00

    CPC classification number: G21C15/243 ,  G21C1/084 ,  G21C1/28 ,  G21C5/02 ,  G21C7/22 ,  G21C9/033 ,  G21C15/24 ,  G21Y2002/201 ,  G21Y2002/601 ,  G21Y2004/40 ,  Y02E30/31 ,  Y02E30/39

    Abstract: A method and system (10) for controlling nuclear reactivity in a nuclear reactor are disclosed. The method includes maintaining a nuclear poison solution at an initial poison pressure (P1) less than the steam pressure within the reactor vessel. The method further includes channeling a pressurizing fluid into the holding tank (12) for pressurizing the poison solution to a pressure greater than the initial pressure thereof, and draining by gravity the poison solution from the holding tank and into the reactor vessel for mixing with the water to reduce reactivity in the core. The system includes the holding tank (12) apparatus for channeling the pressurizing fluid (18) from the reactor vessel (100) to the holding tank, apparatus for channeling the poison solution (28) from the holding tank by gravity into the reactor vessel, and a controller (42) for opening a normally closed pressurizing valve (26) and a normally closed drain valve (40) to allow flow of pressurizing fluid to, and the drained poison solution from, the holding tank through the respective channeling apparatus.

    HYDRAULIC CONTROL ROD DRIVE
    285.
    发明申请
    HYDRAULIC CONTROL ROD DRIVE 审中-公开
    液压控制杆驱动

    公开(公告)号：WO1992001294A1

    公开(公告)日：1992-01-23

    申请号：PCT/US1991004643

    申请日：1991-06-28

    Applicant: GENERAL ELECTRIC COMPANY

    Inventor： GENERAL ELECTRIC COMPANY ,  DILLMANN, Charles, Warner

    IPC: G21C07/16

    CPC classification number: G21C15/243 ,  G21C1/084 ,  G21C1/28 ,  G21C5/02 ,  G21C7/16 ,  G21C15/24 ,  G21Y2002/201 ,  G21Y2002/601 ,  G21Y2004/40 ,  Y02E30/31 ,  Y02E30/39

    Abstract: A drive (10) for positioning a control rod (12) in a nuclear reactor is disclosed. The drive (10) includes a housing (112) having a piston disposed therein, with a piston rod extending from the piston and through the housing for being joinable to the control rod. A driving fluid is provided into the housing for exerting a pressure force against the piston for moving the piston and the control rod. The output requirements for the driving fluid are varied in response to the position of the piston for selectively controlling intermediate positons of the piston.

    Abstract translation: 公开了一种用于将控制杆（12）定位在核反应堆中的驱动装置（10）。 驱动器（10）包括具有设置在其中的活塞的壳体（112），活塞杆从活塞延伸并且通过壳体以可连接到控制杆。 驱动流体被提供到壳体中以对活塞施加压力以移动活塞和控制杆。 驱动流体的输出要求响应于用于选择性地控制活塞的中间位置的活塞的位置而变化。

    TECHNIQUES FOR ON-DEMAND PRODUCTION OF MEDICAL ISOTOPES SUCH AS MO-99/TC-99M AND RADIOACTIVE IODINE ISOTOPES INCLUDING I-131
    286.
    发明申请
    TECHNIQUES FOR ON-DEMAND PRODUCTION OF MEDICAL ISOTOPES SUCH AS MO-99/TC-99M AND RADIOACTIVE IODINE ISOTOPES INCLUDING I-131 审中-公开
    用于医疗同种异体生产的技术如MO-99 / TC-99M和放射性碘同位素包括I-131

    公开(公告)号：WO2011093938A2

    公开(公告)日：2011-08-04

    申请号：PCT/US2010/056573

    申请日：2010-11-12

    Applicant: MIPOD NUCLEAR INC. ,  TSANG, Francis Yu-Hei

    Inventor： TSANG, Francis Yu-Hei

    IPC: G21G4/02

    CPC classification number: G21G1/08 ,  G21G1/001 ,  G21G1/06 ,  G21G4/02 ,  G21G2001/0036 ,  G21G2001/0042 ,  G21G2001/0063 ,  G21Y2002/201

    Abstract: A system for radioisotope production uses fast-neutron-caused fission of depleted or naturally occurring uranium targets in an irradiation chamber. Fast fission can be enhanced by having neutrons encountering the target undergo scattering or reflection to increase each neutron's probability of causing fission (n, f) reactions in U-238. The U-238 can be deployed as layers sandwiched between layers of neutron-reflecting material, or as rods surrounded by neutron-reflecting material. Possible radioisotopes include Mo 99/Tc 99m, I-131, I-132, and I-133.

    Abstract translation: 用于放射性同位素生产的系统在照射室中使用快中子引起的耗尽或天然存在的铀靶的裂变。 通过使遇到目标的中子发生散射或反射以增加每个中子在U-238中引起裂变（n，f）反应的概率，可以提高快速裂变。 U-238可以部署为夹在中子反射材料层之间的层，或者被中子反射材料包围的杆。 可能的放射性同位素包括Mo 99 / Tc 99m，I-131，I-132和I-133。

    低放射化水硬性組成物、低放射化セメント、及びそれらの製造方法
    288.
    发明申请
    低放射化水硬性組成物、低放射化セメント、及びそれらの製造方法 审中-公开
    低活性液压组合物，低活性水泥及其生产方法

    公开(公告)号：WO2008114877A1

    公开(公告)日：2008-09-25

    申请号：PCT/JP2008/055346

    申请日：2008-03-17

    Applicant: 電気化学工業株式会社 ,  森泰一郎 ,  吉野亮悦 ,  樋口隆行

    Inventor： 森泰一郎 ,  吉野亮悦 ,  樋口隆行

    IPC: G21F1/04 ,  C04B7/345

    CPC classification number: C04B7/345 ,  C04B2111/00862 ,  G21F1/042 ,  G21Y2002/201 ,  G21Y2004/10 ,  G21Y2004/40

    Abstract: 放射線遮蔽性能を有する低放射化セメントコンクリート構造物を提供することを課題とする。　カルシウムアルミノシリケートの化学組成が、ＣａＯ、Ａｌ 2 Ｏ 3 、ＳｉＯ 2 、ＭｇＯ、及びＺｒＯ 2 の合計中、ＣａＯが２５～５５部、Ａｌ 2 Ｏ 3 が１６～４５部、ＳｉＯ 2 が２３～４０部、ＭｇＯが０～１部、ＺｒＯ 2 が０～４部であり、カルシウムアルミノシリケート中、Ｅｕ含有量が０．３ｍｇ/ｋｇ未満、Ｃｏ含有量が１５ｍｇ／ｋｇ未満である低放射化水硬性組成物及びその製造方法である。カルシウムアルミナシリケートのガラス化率が７０％以上であり、遊離酸化カルシウムの含有量がカルシウムアルミネートシリケート中０～２部未満であることが好ましい。石膏やセメントを含有しても良い。　

    Abstract translation: 公开了具有辐射屏蔽能力的低活化水泥混凝土结构。 具体公开了一种低活化水硬定型组合物，其包含具有以下化学组成的硅铝酸钙：25至55份CaO，16至45份Al 2 O 3 O 3 ，相对于这些成分的总量，SiO 2为23〜40份，MgO为0〜1份，ZrO 2为0〜4份，其中硅铝酸钙 Eu含量小于0.3mg / kg，Co含量小于15mg / kg。 还具体公开了一种制备该组合物的方法。 优选地，硅铝酸钙的玻璃化率为70％以上，游离氧化钙含量小于2份。 组合物还可以包含目标（硫酸钙）或水泥。

    CONTAINMENT VESSEL AND METHOD FOR OPERATING A CONDENSER IN A NUCLEAR POWER PLANT
    289.
    发明申请
    CONTAINMENT VESSEL AND METHOD FOR OPERATING A CONDENSER IN A NUCLEAR POWER PLANT 审中-公开
    遏制和一种用于操作电容核电站

    公开(公告)号：WO9945546A9

    公开(公告)日：2008-09-18

    申请号：PCT/DE9900447

    申请日：1999-02-18

    Applicant: SIEMENS AG ,  MESETH JOHANN

    Inventor： MESETH JOHANN

    IPC: G21C9/004 ,  G21C15/18

    CPC classification number: G21C15/18 ,  G21C9/004 ,  G21Y2002/201 ,  G21Y2002/207 ,  G21Y2002/301 ,  G21Y2004/30 ,  G21Y2004/402 ,  Y02E30/31

    Abstract: In order to carry off noncondensible gases from the surroundings of a building condenser (16) in a containment vessel (1) of a boiling water nuclear power plant while preserving the reliability of performance of the building condenser (16), a drain pipe (22) is provided that connects the upper area in the containment vessel (1) to a condensing chamber (4) arranged in the containment vessel (1). The noncondensible gases flow automatically through the drain pipe into the condensing chamber (4). The building condenser can thus be structured in a simple and economical manner.

    Abstract translation: 在从在密闭容器（1）建筑物电容器（16）的附近，以便导出一个沸水核电厂的不可冷凝的气体，并因此获得建筑物电容器的功能（16）直立，排出管（22）设置（在容纳上部 结合1）设置以与一个（在所属1）冷凝腔室（4）。 所述非冷凝气体流过排出管自动进入冷凝腔室（4）。 该建筑电容器（16）可以简单且廉价地进行配置。

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