Method for calibrating steam generator water level measurement
    71.
    发明授权
    Method for calibrating steam generator water level measurement 有权
    蒸汽发生器水位测量校准方法

    公开(公告)号:US07120218B2

    公开(公告)日:2006-10-10

    申请号:US10647757

    申请日:2003-08-25

    Abstract: A method is provided for determining and controlling feed water level in a steam generator of a nuclear power plant, whereby the water level sensor is calibrated in terms of the pressure drop across structural components in the feed water path. The water level differential pressure sensor is calibrated so that maximum water level is indicated as the level corresponding to the upper tap level plus the pressure drop across the foregoing structural components at maximum power plant power.

    Abstract translation: 提供了一种用于确定和控制核电厂的蒸汽发生器中的给水水平的方法,由此水位传感器根据供水路径中的结构部件的压降进行校准。 校准水位差压传感器,使得最大水位被指示为对应于最高水位电平的水平加上在最大发电厂功率下的上述结构组件上的压降。

    Working device and working method
    72.
    发明申请
    Working device and working method 有权
    工作装置和工作方法

    公开(公告)号:US20060222138A1

    公开(公告)日:2006-10-05

    申请号:US11270832

    申请日:2005-11-10

    Abstract: A working apparatus has: a working equipment for doing works on a structure; an operation mechanism adapted to actively move the working equipment relative to the structure; and an adhering/traveling module coupled to the operation mechanism and adapted to adhere to the structure so as to have the weight of the working apparatus borne by the structure and travel/move on the structure for positioning. With this arrangement, the working apparatus can perform accurate positioning operations in a narrow environment and complex scanning operations by means of various pieces of the working equipment such as inspection sensors, and can secure a large working area within a short period of time and reduce the overall working hours.

    Abstract translation: 工作设备有:在结构上进行工作的工作设备; 适于主动地移动工作设备相对于结构的操作机构; 以及粘接/移动模块,其联接到所述操作机构并且适于粘附到所述结构,以使得所述工作装置的重量由所述结构承载并且在所述结构上行进/移动以进行定位。 通过这种布置,工作装置可以通过诸如检查传感器的各种工作设备在狭窄的环境中执行精确的定位操作和复杂的扫描操作,并且可以在短时间内确保大的工作区域并且减少 整体工作时间

    SYSTEM AND METHOD FOR CHEMICAL DECONTAMINATION OF RADIOACTIVE MATERIAL
    74.
    发明申请
    SYSTEM AND METHOD FOR CHEMICAL DECONTAMINATION OF RADIOACTIVE MATERIAL 有权
    放射性物质化学去除的系统与方法

    公开(公告)号:US20060167330A1

    公开(公告)日:2006-07-27

    申请号:US10717628

    申请日:2003-11-21

    Abstract: A method for chemically decontaminating radioactive material. The method includes reducing-dissolving step for setting surface of radioactive material in contact with reducing decontamination liquid including mono-carboxylic acid and di-carboxylic acid as dissolvent; and oxidizing-dissolving step for setting the surface of the radioactive material in contact with oxidizing decontamination liquid including oxidizer. The method may include repeated pairs of steps, each pair including the reducing-dissolving step and the oxidizing-dissolving step. The mono-carboxylic acid may include formic acid, and the di-carboxylic acid includes oxalic acid. The oxidizer may be ozone, permanganic acid or permanganate.

    Abstract translation: 一种化学去除放射性物质的方法。 该方法包括用于使放射性物质的表面与包含单羧酸和二羧酸的还原性去污液接触的还原溶解步骤作为溶剂; 以及用于使放射性物质的表面与包括氧化剂的氧化性去污液接触的氧化溶解步骤。 该方法可以包括重复的步骤对,每对包括还原溶解步骤和氧化溶解步骤。 单羧酸可以包括甲酸,二羧酸包括草酸。 氧化剂可以是臭氧,高锰酸或高锰酸盐。

    Method for determining threshold value of a nuclear reactor operating parameter, corresponding system, computer programme and support
    75.
    发明申请
    Method for determining threshold value of a nuclear reactor operating parameter, corresponding system, computer programme and support 有权
    确定核反应堆运行参数,相应系统,计算机程序和支持阈值的方法

    公开(公告)号:US20060129362A1

    公开(公告)日:2006-06-15

    申请号:US10532272

    申请日:2003-10-13

    Abstract: A method of determining a threshold value of a nuclear reactor operating parameter having the steps of simulating at least a transient operational occurrence of the nuclear reactor, calculating the value reached by a physical quantity during the transient operational occurrence in at least a cladding of a fuel rod of the reactor and establishing, as a limit value of an operational parameter of the reactor, the value of the operational parameter when the value calculated the step of calculating the value reached by a physical quantity during the transient operational occurrence which corresponds to a value of the physical quantity which characterizes a failure of the cladding.

    Abstract translation: 一种确定核反应堆操作参数的阈值的方法,该方法具有以下步骤:至少模拟核反应堆的瞬时操作发生,计算在燃料的至少一个包层中的瞬态操作发生期间由物理量达到的值 并且当所述值计算在瞬时操作发生期间由物理量达到的值对应于值时计算出所述值的步骤,确定所述操作参数的值作为所述反应器的操作参数的极限值 表现为包层故障的物理量。

    Method and algorithm for searching and optimizing nuclear reactor core loading patterns
    76.
    发明申请
    Method and algorithm for searching and optimizing nuclear reactor core loading patterns 有权
    核反应堆核心装载模式的搜索和优化方法和算法

    公开(公告)号:US20060109944A1

    公开(公告)日:2006-05-25

    申请号:US10993249

    申请日:2004-11-19

    Applicant: Frank Popa

    Inventor: Frank Popa

    CPC classification number: G21C19/205 G21Y2002/201 G21Y2002/304 G21Y2004/40

    Abstract: A method is for establishing a nuclear reactor core loading pattern (LP) for fuel assemblies and burnable absorbers (BAs). The method establishes an optimum LP through the steps of: a) providing nuclear data representing fuel assemblies and BAs in a nuclear reactor core; b) depleting the nuclear data to form a reference core depletion; c) incorporating the nuclear data into a system of linear equations of a nuclear design quality flux solution method; d) defining the system of linear equations to include constraints which accurately represent the neutron physics of the reactor; employing the equations as a constraint matrix for a MIP solver to find an optimum core pattern solution; f) repeating steps b) through e) updating the constraints and objective functions to satisfy specified engineering requirements and establish an optimum core loading pattern. An algorithm for deriving the system of equations is also disclosed.

    Abstract translation: 一种用于建立燃料组件和可燃吸收器(BAs)的核反应堆堆芯装载模式(LP)的方法。 该方法通过以下步骤建立最佳LP:a)在核反应堆核心中提供代表燃料组件和BAs的核数据; b)消耗核数据以形成参考核心耗尽; c)将核数据纳入核设计质量通量溶液法线性方程组; d)定义线性方程组,以包括精确表示反应堆中子物理学的约束; 采用方程作为MIP求解器的约束矩阵以找到最佳核心图案解; f)重复步骤b)至e)更新约束和目标函数以满足规定的工程要求并建立最佳的核心加载模式。 还公开了用于导出方程组的算法。

    Jet pump assembly repair method
    78.
    发明授权
    Jet pump assembly repair method 有权
    喷气泵组装维修方法

    公开(公告)号:US07023949B2

    公开(公告)日:2006-04-04

    申请号:US10830452

    申请日:2004-04-22

    Inventor: Adrian P. Wivagg

    Abstract: A BWR jet pump assembly has a wedge slidably mounted on a jet pump that is movable under the force of gravity to seat between a bracket and the jet pump in order to horizontally support the jet pump against vibrations. The wedge or the bracket is repaired in situ by: providing a spacer layer between mating surfaces of the wedge and the bracket; and then lowering the wedge until the spacer layer is between and in contact with the wedge and the bracket.

    Abstract translation: BWR喷射泵组件具有可滑动地安装在喷射泵上的楔块,该喷射泵可在重力作用下移动以支撑在支架和喷射泵之间,以便水平地支撑喷射泵免受振动。 通过以下步骤来修复楔形物或支架:在楔形物和支架的配合表面之间提供间隔层; 然后降下楔形件直到间隔层在楔形件和支架之间并且与楔块和支架接触。

    Screened chamber for ion therapy
    80.
    发明申请
    Screened chamber for ion therapy 有权
    离子疗法筛选室

    公开(公告)号:US20050218348A1

    公开(公告)日:2005-10-06

    申请号:US11046648

    申请日:2005-01-28

    Abstract: In a shielded chamber for neutron therapy including a therapy room which has a main axis as determined by the direction of a high-energy neutron therapy beam surrounded by shielding and includes at one end a labyrinth entrance with at least two shielding wall sections displaced longitudinally along the main axis and extending into the room from opposite side walls, the wall sections include means for causing spallation of the incident high energy neutrons to thereby generate from the high energy neutrons in the high energy neutron beam a plurality of low energy neutrons which are then moderated.

    Abstract translation: 在用于中子治疗的屏蔽室中,包括治疗室,该治疗室具有由屏蔽包围的高能中子治疗束的方向确定的主轴,并且在一端具有迷宫入口,其中至少两个屏蔽壁部分沿纵向移动 主轴线并从相对的侧壁延伸到房间中,壁部分包括用于引起入射的高能中子的散裂的装置,从而从高能中子束中的高能中子产生多个低能中子 主持人

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