公开(公告)号：US08067659B2

公开(公告)日：2011-11-29

申请号：US11871090

申请日：2007-10-11

Applicant: Krishna P. Singh ,  Stephen J. Agace

Inventor： Krishna P. Singh ,  Stephen J. Agace

IPC: G21F9/00 ,  G21F1/00 ,  G21F9/20 ,  G21C19/00

CPC classification number: G21F5/005 ,  G21F5/10 ,  G21Y2002/201 ,  G21Y2002/501 ,  G21Y2004/30

Abstract: A system, apparatus and method of processing and/or removing radioactive materials from a body of water that utilizes the buoyancy of the water itself to minimize the load experienced by a crane and/or other lifting equipment. In one aspect, the invention is a method comprising: a) submerging a container having a top, a bottom, and a cavity in a body of water having a surface level, the cavity filling with water; b) positioning radioactive material within the cavity of the submerged container; c) raising the submerged container until the top of the containment apparatus is above the surface level of the body of water while a major portion of the container remains below the surface level of the body of water; and d) removing bulk water from the cavity while the top of the container remains above the surface level of the body of water and a portion of the container remains submerged. The bulk water can be added back into the cavity to add neutron shielding after the container is placed in a staging area and prior to personnel performing the desired operations to the container. As a result, gamma radiation and neutron shielding of the container can be maximized for any crane capacity.

Abstract translation: 一种利用水本身的浮力来处理和/或从水体中去除放射性物质的系统，装置和方法，以最小化起重机和/或其他提升设备所经历的负载。 一方面，本发明是一种方法，其包括：a）将具有顶部，底部和空腔的容器浸没在具有表面水平的水体中，所述空腔充满水; b）将放射性物质放置在浸没的容器的腔内; c）升起浸没的容器直到容纳装置的顶部高于水体的表面水平，同时容器的主要部分保持在水体的表面水平以下; 以及d）当容器的顶部保持在水体的表面水平面上并且容器的一部分保持浸没时，从空腔中移出大量的水。 在将容器放置在分段区域中之后并且在人员对容器进行所需操作之前，可以将大量的水加回空腔中以加入中子屏蔽。 结果，对于任何起重机的容量，可以使容器的伽马辐射和中子屏蔽最大化。

公开(公告)号：US20110280358A1

公开(公告)日：2011-11-17

申请号：US13192606

申请日：2011-07-28

Applicant: Masaya OHTSUKA ,  Kiyoshi Fujimoto ,  Masaaki Tsubaki

Inventor： Masaya OHTSUKA ,  Kiyoshi Fujimoto ,  Masaaki Tsubaki

IPC: G21C17/00 ,  G21C9/004

CPC classification number: G21C17/00 ,  G21C17/02 ,  G21D3/001 ,  G21D3/08 ,  G21Y2002/201 ,  G21Y2002/207 ,  G21Y2002/303 ,  G21Y2004/40 ,  G21Y2004/403 ,  Y02E30/39

Abstract: A method for monitoring and acoustic damping a boiling water reactor which includes: a reactor pressure vessel; a steam pipe for transporting steam out from a steam dome of the reactor pressure vessel; a high pressure turbine driven by the steam; a feedwater heater which heats feedwater supplied to the reactor pressure vessel using bleed steam from the high pressure turbine; a bleeding valve which adjusts a flow rate of the bleed steam; and a pressure sensor provided in a main steam line including the steam dome and the steam pipe. The method includes monitoring a fluctuating pressure in the main steam line and controlling an opening degree of the bleeding valve based on a magnitude of the fluctuating pressure.

Abstract translation: 一种用于沸水反应器的监测和声阻尼的方法，包括：反应堆压力容器; 蒸汽管，用于将蒸汽从反应堆压力容器的蒸汽圆顶运出; 由蒸汽驱动的高压涡轮机; 给水加热器，其使用来自高压涡轮机的排出蒸汽加热供应到反应堆压力容器的给水; 调节排出蒸汽的流量的排出阀; 以及设置在包括蒸汽穹顶和蒸汽管的主蒸汽管线中的压力传感器。 该方法包括监测主蒸汽管线中的波动压力并基于波动压力的大小来控制排气阀的开度。

公开(公告)号：US07997078B2

公开(公告)日：2011-08-16

申请号：US12574219

申请日：2009-10-06

Applicant: Masao Chaki ,  Kazuaki Kitou ,  Motoo Aoyama ,  Masaya Ootsuka ,  Kouji Shiina

Inventor： Masao Chaki ,  Kazuaki Kitou ,  Motoo Aoyama ,  Masaya Ootsuka ,  Kouji Shiina

IPC: G21D5/00 ,  F01K7/34

CPC classification number: G21C1/084 ,  G21D1/02 ,  G21D3/00 ,  G21Y2002/201 ,  G21Y2002/304 ,  G21Y2004/30 ,  G21Y2004/40 ,  Y02E30/31 ,  Y02E30/39

Abstract: In a nuclear power plant, thermal power in a second operation cycle of a nuclear reactor is uprated from thermal power in a first operation cycle preceding the second operation cycle by at least one operation cycle. A proportion of steam extracted from a steam system and introduced to a feedwater heater, which is in particular extracted from an intermediate point and an outlet of a high pressure turbine, with respect to a flow rate of main steam, is reduced in the second operation cycle from that in the first operation cycle such that the temperature of feedwater discharged from the feedwater heater is lowered by 1° C. to 40° C. in the second operation cycle.

Abstract translation: 在核电站中，核反应堆的第二操作循环中的热功率在第二操作周期之前的第一操作周期内从热功率上升至少一个操作周期。 在蒸汽系统中提取的蒸汽的比例相对于主蒸汽的流量被引入特定从高压汽轮机的中间点和出口抽出的给水加热器在第二操作 循环，从而在第二操作循环中使得从给水加热器排出的给水温度降低1℃至40℃。

公开(公告)号：US20110162363A1

公开(公告)日：2011-07-07

申请号：US13046294

申请日：2011-03-11

Applicant: Masao CHAKI ,  Kazuaki KITOU ,  Motoo AOYAMA ,  Masaya OOTSUKA ,  Kouji SHIINA

Inventor： Masao CHAKI ,  Kazuaki KITOU ,  Motoo AOYAMA ,  Masaya OOTSUKA ,  Kouji SHIINA

IPC: G21D5/00 ,  F01K23/02

CPC classification number: G21C1/084 ,  G21D1/02 ,  G21D3/00 ,  G21Y2002/201 ,  G21Y2002/304 ,  G21Y2004/30 ,  G21Y2004/40 ,  Y02E30/31 ,  Y02E30/39

Abstract: In a nuclear power plant, thermal power in a second operation cycle of a nuclear reactor is uprated from thermal power in a first operation cycle preceding the second operation cycle by at least one operation cycle. A proportion of steam extracted from a steam system and introduced to a feedwater heater, which is in particular extracted from an intermediate point and an outlet of a high pressure turbine, with respect to a flow rate of main steam, is reduced in the second operation cycle from that in the first operation cycle such that the temperature of feedwater discharged from the feedwater heater is lowered by 1° C. to 40° C. in the second operation cycle.

Abstract translation: 在核电站中，核反应堆的第二操作循环中的热功率在第二操作周期之前的第一操作周期内从热功率上升至少一个操作周期。 在蒸汽系统中提取的蒸汽的比例相对于主蒸汽的流量被引入特定从高压汽轮机的中间点和出口抽出的给水加热器在第二操作 循环，从而在第二操作循环中使得从给水加热器排出的给水温度降低1℃至40℃。

公开(公告)号：US20110116590A1

公开(公告)日：2011-05-19

申请号：US12096364

申请日：2006-12-07

Applicant: Alain Dictor ,  Marc Fischer

Inventor： Alain Dictor ,  Marc Fischer

IPC: G21F9/00

CPC classification number: G21F9/00 ,  G21C21/02 ,  G21F9/005 ,  G21Y2002/201 ,  G21Y2002/205 ,  G21Y2002/304 ,  G21Y2004/30 ,  G21Y2004/40

Abstract: A method for the surface tribological decontamination of nuclear fuel rods automates surface wiping by one or more bands of fabric. The band is distant from the axis of the rod, the rod is placed facing the band, and then the band is tensioned around the surface of the rod and moved. The rod may be immobile, moved in pure translation along its axis or with a wide-step helical movement. Preferably, the decontamination is carried by two bands simultaneously, so as to cover the total surface in one pass of the rod.

Abstract translation: 核燃料棒的表面摩擦学去污的方法使织物的一个或多个带的表面擦拭自动化。 该带远离杆的轴线，杆被放置成面向带，然后带在杆的表面周围张紧并移动。 杆可以是不动的，沿其轴线以宽的螺旋运动以纯平移方式移动。 优选地，去污被同时由两个带承载，以便覆盖杆的一次通过中的总表面。

公开(公告)号：US07926345B2

公开(公告)日：2011-04-19

申请号：US12325447

申请日：2008-12-01

Applicant: Sacha Kaercher ,  Wolfgang Vogt ,  Wilfried Harfst

Inventor： Sacha Kaercher ,  Wolfgang Vogt ,  Wilfried Harfst

IPC: G01F23/00

CPC classification number: G01F23/22 ,  G01F23/248 ,  G21C1/08 ,  G21C17/035 ,  G21Y2002/201 ,  G21Y2002/204 ,  G21Y2002/304 ,  G21Y2004/30 ,  Y02E30/40

Abstract: An apparatus for measuring the filling level in a liquid vessel, in particular in a reactor vessel of a nuclear-engineering plant, with a plurality of elongate, spaced-apart measurement tubes. Each measurement tube has a number of thermocouples which are distributed in the longitudinal direction. A thermocouple, which acts as a primary signal transmitter, is heated by a heating element and is arranged on a first measurement tube, has assigned to it on the signal side an unheated thermocouple, which acts as a reference signal transmitter and is arranged on a measurement tube which is different from the first measurement tube.

Abstract translation: 一种用于测量液体容器中的填充水平的装置，特别是在核工程设备的反应器容器中，具有多个细长间隔开的测量管。 每个测量管具有沿纵向方向分布的多个热电偶。 作为主要信号发射器的热电偶被加热元件加热，并且被布置在第一测量管上，在信号侧分配有未加热的热电偶，其作为参考信号发射器并被布置在 测量管与第一测量管不同。

公开(公告)号：US07923708B2

公开(公告)日：2011-04-12

申请号：US11816778

申请日：2006-02-16

Applicant: Eiji Oyaizu

Inventor： Eiji Oyaizu

IPC: G21F5/00

CPC classification number: G21F1/10 ,  G21Y2002/201 ,  G21Y2002/302 ,  G21Y2004/10

Abstract: A radiation shielding sheet formed by filling a shielding material into an organic polymer material. The shielding material is an oxide powder containing at least one element selected from the group consisting of lanthanum (La), cerium (Ce), praseodymium (Pr), neodymium (Nd), samarium (Sm), europium (Eu) and gadolinium (Gd). The oxide powder has an average grain size of 1 to 20 μm, and a volumetric ratio of the shielding material filled in the radiation shielding sheet is 40 to 80 vol. %.

Abstract translation: 通过将屏蔽材料填充到有机聚合物材料中形成的辐射屏蔽片。 屏蔽材料是含有选自镧（La），铈（Ce），镨（Pr），钕（Nd），钐（Sm），铕（Eu）和钆（镧）的至少一种元素的氧化物粉末 Gd）。 氧化物粉末的平均粒径为1〜20μm，填充在辐射屏蔽片中的屏蔽材料的体积比为40〜80体积％。 ％。

公开(公告)号：US07860206B2

公开(公告)日：2010-12-28

申请号：US11657459

申请日：2007-01-25

Applicant: Atsushi Fushimi ,  Setsuo Arita ,  Kazuhiko Ishiii ,  Yoshihiko Ishii ,  Shin Hasegawa ,  Atsutoshi Mizuide

Inventor： Atsushi Fushimi ,  Setsuo Arita ,  Kazuhiko Ishiii ,  Yoshihiko Ishii ,  Shin Hasegawa ,  Atsutoshi Mizuide

IPC: G21C7/36

CPC classification number: G21C1/084 ,  G21C7/36 ,  G21D3/08 ,  G21Y2002/201 ,  G21Y2004/30 ,  G21Y2004/40 ,  Y02E30/31 ,  Y02E30/39

Abstract: In order to provide a reactor power control apparatus which can maintain a stable water level when reactivity control based on control rod operation and water level adjustment is performed, this invention comprises a turbine control which calculates the load set error signal from the error between the set target generator power value and the generator power that was fed back and outputs to the turbine control apparatus; control rod control in the natural circulation boiling water reactor which calculates the control rod operation signal and outputs it to the control rod drive control apparatus; water level control inside the natural circulation boiling water reactor which calculates the water level set signal and outputs it to the feed water control apparatus; and the switch determining device which selectively outputs one of the control rod control and water level control based on the generator power that was fed back, the reactor power and water level, as well as switching rules and determination values.

Abstract translation: 为了提供一种在基于控制杆操作和水位调节的反应性控制时可以保持稳定的水位的反应堆功率控制装置，本发明包括一个涡轮机控制装置，该装置根据装置的误差计算负载设定误差信号 目标发电机功率值和反馈并输出到涡轮机控制装置的发电机功率; 控制棒控制在自然循环沸水反应堆中，计算控制棒的运行信号，并将其输出到控制棒驱动控制装置; 自然循环沸水反应堆内的水位控制，其计算水位设定信号并输出​​给给水控制装置; 以及切换判定装置，其基于反馈的发电机功率，反应堆功率和水位以及切换规则和判定值选择性地输出控制棒控制和水位控制中的一个。

公开(公告)号：US20100296620A1

公开(公告)日：2010-11-25

申请号：US12776599

申请日：2010-05-10

Applicant: Per F. Peterson

Inventor： Per F. Peterson

IPC: G21C15/247 ,  G21C1/02 ,  G21C3/04 ,  G21C11/06

CPC classification number: G21C3/30 ,  G21C1/07 ,  G21C3/22 ,  G21C7/107 ,  G21Y2002/201 ,  G21Y2002/301 ,  G21Y2004/30 ,  Y02E30/36

Abstract: A high-temperature nuclear reactor, cooled by a liquid fluoride salt, is described. The reactor uses an annular fuel pebble comprised of an inert graphite center kernel, a TRISO fuel particles region, and a graphite outer shell, with an average pebble density lower than the density of the liquid salt so the pebbles float. The pebbles are introduced into a coolant entering the reactor and are carried into the bottom of the reactor core, where they form a pebble bed inside a plurality of vertical channels inside one or more replaceable Pebble Channel Assemblies (PCAs). Pebbles are removed through defueling chutes located at the top of each PCA. Each PCA also includes channels for insertion of neutron control and shutdown elements, and channels for insertion of core flux mapping and other instrumentation.

Abstract translation: 描述了由液态氟化物盐冷却的高温核反应堆。 反应器使用由惰性石墨中心核，TRISO燃料颗粒区域和石墨外壳组成的环形燃料卵石，其平均卵石密度低于液体盐的密度，以使卵石浮动。 鹅卵石被引入到进入反应器的冷却剂中并被运送到反应堆堆芯的底部，在反应堆堆芯的底部，它们在一个或多个可更换的卵石通道组件（PCAs）内的多个垂直通道内形成卵石床。 通过位于每个PCA顶部的排污槽来移除卵石。 每个PCA还包括用于插入中子控制和关闭元件的通道，以及用于插入核心通量映射和其他仪器的通道。

公开(公告)号：US20100290577A1

公开(公告)日：2010-11-18

申请号：US12280286

申请日：2007-02-22

Applicant: Ronald H. Baney ,  James S. Tulenko ,  Kevin W. Powers

Inventor： Ronald H. Baney ,  James S. Tulenko ,  Kevin W. Powers

IPC: G21C15/28 ,  C09K5/10

CPC classification number: G21C15/28 ,  G21Y2002/201 ,  G21Y2002/304 ,  G21Y2004/302 ,  G21Y2004/40 ,  Y02E30/40

Abstract: A pressurized water nuclear reactor (PWNR) 100 includes a core having a containment shield 105 surrounding a reactor vessel 110 having fuel assemblies that contain fuel rods filled with fuel pellets 115, and control rods 118, and a steam generator 120 thermally coupled to the reactor vessel 110. A flow loop includes the steam generator 120, a turbine 130, and a condenser 135, and a pump 140 for circulating a water-based heat transfer fluid 145 in the loop. The heat transfer fluid 145 includes a plurality of nanoparticles having at least one carbon allotrope or related carbon material dispersed therein, such as diamond nanoparticles.

Abstract translation: 加压水核反应堆（PWNR）100包括具有围绕反应堆容器110的容纳屏蔽件105的芯体，反应器110具有燃料组件，该燃料组件包含填充有燃料颗粒115的燃料棒，以及控制棒118和与反应器热耦合的蒸汽发生器120 流动回路包括蒸汽发生器120，涡轮130和冷凝器135，以及用于在循环中循环水基传热流体145的泵140。 传热流体145包括具有分散在其中的至少一种碳同素异形体或相关碳材料的多个纳米颗粒，例如金刚石纳米颗粒。