Systems and methods for assaying an eluate for technetium and molybdenum content
    5.
    发明授权
    Systems and methods for assaying an eluate for technetium and molybdenum content 有权
    用于测定锝和钼含量的洗脱液的系统和方法

    公开(公告)号:US09285487B2

    公开(公告)日:2016-03-15

    申请号:US14524196

    申请日:2014-10-27

    CPC classification number: G01T1/185 G01T7/02 G21F5/015

    Abstract: A system for assaying an eluate for Technetium-99m and Molybdenum-99 content includes an inner ionization chamber including a well configured to receive the eluate, an outer ionization chamber concentric with the inner ionization chamber, and attenuating material positioned between the inner and outer ionization chambers. A computing device is configured to determine a Technetium-99m content of the eluate based on a first current measured in the inner ionization chamber, and determine a Molybdenum-99 content of the eluate based on at least a second current measured in the outer ionization chamber.

    Abstract translation: 用于测定锝-99m和钼-99含量的洗脱液的系统包括内部电离室,其包括良好构造成接收洗脱液的内部电离室,与内部电离室同心的外部电离室,以及位于内部和外部电离之间的衰减材料 房间。 计算装置被配置为基于在内部电离室中测量的第一电流来确定洗脱物的锝-99m含量,并且基于在外部电离室中测量的至少第二电流来确定洗脱液的钼-99含量 。

    NUCLEAR REACTOR FUEL INTEGRITY MONITOR
    6.
    发明申请
    NUCLEAR REACTOR FUEL INTEGRITY MONITOR 有权
    核反应堆燃料完整性监测

    公开(公告)号:US20150115157A1

    公开(公告)日:2015-04-30

    申请号:US14520887

    申请日:2014-10-22

    Abstract: A nuclear reactor fuel integrity monitor includes: a γ-ray detector which detects γ-ray of a specific radionuclide of a subject measurement medium of a nuclear reactor; a sample container which retains the subject measurement medium therein and surrounds the circumference of the γ-ray detector; and a measurement control device which performs a control so that a predetermined amount of the subject measurement medium is introduced into the sample container and calculates a concentration of the specific radionuclide from γ-ray data per each unit time detected by the γ-ray detector and a volume of the subject measurement medium introduced into the sample container.

    Abstract translation: 核反应堆燃料完整性监视器包括:γ射线检测器,其检测核反应堆的被测量介质的特定放射性核素的γ射线; 样本容器,其将被检测体介质保持在其中并且包围γ射线检测器的周围; 以及测量控制装置,其进行控制,使得将预定量的被摄体测量介质引入到样本容器中,并根据由γ射线检测器检测的每单位时间的γ射线数据计算特定放射性核素的浓度;以及 将被测量介质的体积引入到样品容器中。

    Device and Method for Determining Activity of Radiopharmaceutical Material
    7.
    发明申请
    Device and Method for Determining Activity of Radiopharmaceutical Material 有权
    放射性药物材料活性测定装置及方法

    公开(公告)号:US20120074330A1

    公开(公告)日:2012-03-29

    申请号:US12664653

    申请日:2009-12-14

    CPC classification number: G01T7/02 A61M5/007

    Abstract: A detector system measures radioactive material. A fluid path receives at least one aliquot of radiopharmaceutical. The fluid path locates the aliquot within a positioner formed with a concave configuration. A detector is located at an axial distance from the concave surface and determines the level of radioactivity of the aliquot. Alternatively, the fluid path may be less concave and a variable attenuator may be placed between the fluid path and detector. The variable attenuator may have a concavity that is based on the concavity of the fluid path so that the detector's ability to read the radioactivity is optimized. A method for forming an aliquot of radiopharmaceutical in a concave fluid passage. Positioning a detector located a distance from the concave surface to optimize reading spectral energy of the aliquot and activity is determining activity regardless of the position of the aliquot in the passage.

    Abstract translation: 检测器系统测量放射性物质。 流体路径接收至少一个等分的放射性药物。 流体路径将等分试样定位在形成有凹形构型的定位器内。 检测器位于距凹面的轴向距离处,并确定等分试样的放射性水平。 或者,流体路径可以较少凹入,并且可变衰减器可以放置在流体路径和检测器之间。 可变衰减器可以具有基于流体路径的凹部的凹度,使得检测器读取放射性的能力被优化。 还描述了在凹形流体通道中形成放射性药物的等分试样的方法。 定位一个与凹面相距一定距离的检测器,通过确定活动而不考虑通道中等分试样的位置,优化读取等分试样的光谱能量和活性。

    Cell for the analysis of radioactive liquids by an overhanging detector
    8.
    发明授权
    Cell for the analysis of radioactive liquids by an overhanging detector 失效
    用于通过悬臂检测器分析放射性液体的电池

    公开(公告)号:US5726452A

    公开(公告)日:1998-03-10

    申请号:US644943

    申请日:1996-05-13

    CPC classification number: G01T7/02 G01T1/003

    Abstract: Cell, whose interior (3) is filled with liquid, whose radioactivity is measured by a scintillator or other detector install thereon. The invention consists of equipping the cell with rinsing means in order to wash the cell side wall (2) and the sealing or blanking plate (13) with respect to impurities deposited thereon and interfering with the measurement as a result of their natural radioactivity. Blowing means are provided above the free surface of the radioactive liquid in order to oppose its vaporization, which would produce other deposits.

    Abstract translation: 其内部(3)充满液体的电池,其放射性通过安装在其上的闪烁体或其它检测器测量。 本发明包括将电池装配有冲洗装置,以便相对于其上沉积的杂质洗涤电池侧壁(2)和密封或消隐板(13),并且由于其自然放射性而干扰测量。 吹扫装置设置在放射性液体的自由表面之上,以反对其蒸发,这将产生其他沉积物。

    Apparatus for measuring the .alpha. activity of a solution
    9.
    发明授权
    Apparatus for measuring the .alpha. activity of a solution 失效
    用于测量溶液的α活性的装置

    公开(公告)号:US5276332A

    公开(公告)日:1994-01-04

    申请号:US971318

    申请日:1992-11-04

    CPC classification number: G01T7/02

    Abstract: Apparatus for measuring the .alpha. activity of a solution and used for determining the plutonium concentration of a solution sampled from an irradiated nuclear fuel reprocessing installation and which comprises a rotary drum (20), which samples a film of solution in a vessel (20), in order to place it in front of a measuring probe (22). Between the probe (22) and the drum (20) is positioned a sealing disk (40) having three positions, which has an effective measuring region (48), a measuring chain quality checking region and a blank measuring region. In order to avoid a solution deposit by condensation on the disk (40) or on the end of the probe (22), a protective gas injection system (49) having passages traversing the vessel cover (16), scavenges the upper face of the sealing disk at three locations corresponding to the three active regions of the latter. A substantially uniform distribution of the gas flow between said three locations is ensured. The protective gas is then sucked in by a tube (122).

    Abstract translation: 用于测量溶液的α活性并用于确定从经辐照的核燃料再处理装置采样的溶液的钚浓度的装置,其包括在容器(20)中对溶液膜进行采样的旋转滚筒(20) 以便将其放置在测量探头(22)的前面。 在探针(22)和滚筒(20)之间设置有具有三个位置的密封盘(40),该密封盘具有有效测量区域(48),测量链质量检查区域和空白测量区域。 为了避免在盘(40)或探针(22)的端部上的冷凝溶液沉积,具有穿过容器盖(16)的通道的保护气体注入系统(49)清除了 密封盘对应于后者的三个活动区域的三个位置。 确保了在所述三个位置之间的气流的基本均匀的分布。 然后,保护气体被管(122)吸入。

    Automatic radioisotope filling apparatus
    10.
    发明授权
    Automatic radioisotope filling apparatus 失效
    自动放射性同位素灌装装置

    公开(公告)号:US4853546A

    公开(公告)日:1989-08-01

    申请号:US97025

    申请日:1987-09-16

    CPC classification number: G01T7/02 G01N1/38 G21G4/02

    Abstract: An automatic radioisotope filling apparatus which includes a radioisotope vial containing a radioisotope solution, a saline vial containing a physiological saline solution and a plurality of label vials containing a drug into which a predetermined amount of the radioisotope solution or the physiological saline solution is to be filled automatically. A required amount of the radioisotope solution or the physiological saline solution is automatically metered and automatically filled into each label vial and consequently the radiation exposure of the operator of the apparatus is minimized.

    Abstract translation: 一种自动放射性同位素填充装置,其包括含有放射性同位素溶液的放射性同位素小瓶,含有生理盐水的盐水小瓶和含有预定量的放射性同位素溶液或生理盐水溶液的药物的多个标记小瓶 自动。 自动计量所需量的放射性同位素溶液或生理盐水溶液,并自动填充到每个标签小瓶中,从而使装置的操作者的辐射暴露最小化。

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