Use of electrochemical potential to predict radiation buildup on nuclear
reactor coolant piping
    121.
    发明授权
    Use of electrochemical potential to predict radiation buildup on nuclear reactor coolant piping 失效
    使用电化学势来预测核反应堆冷却剂管道的辐射累积

    公开(公告)号:US4759902A

    公开(公告)日:1988-07-26

    申请号:US916382

    申请日:1986-10-07

    申请人: Larry D. Anstine

    发明人: Larry D. Anstine

    IPC分类号: G21C17/022 G21C9/00

    CPC分类号: G21C17/022

    摘要: This invention relates to a method of predicting the long-term dose rates from radioactive material on the interior, wetted surfaces of the primary coolant piping of nuclear power reactors. The electrochemical potential of the cooling water of a nuclear power plant is measured over a short-term period with an electrochemical potential measuring device that has an unprefilmed measuring electrode. The results of these electrochemical potential measurements are divided by the result at a prescribed short period of exposure, and these normalized electrochemical potential fractions are plotted versus the logarithm of time. The negative of the slope of the straight line through the plotted data is divided into the measured average Co-60 concentration in the cooling water, and a standard curve of long-term dose rate versus this parameter is used to predict the eventual long-term radiation build-up performance of the nuclear power plant in which the electrochemical potential measurements are made.

    摘要翻译: 本发明涉及一种预测核动力反应堆主要冷却剂管道的内部润湿表面上的放射性物质的长期剂量率的方法。 利用电化学电位测量装置测量核电站冷却水的电化学势,并在短时间内测量出一个无预测的测量电极。 这些电化学电位测量的结果除以规定的短时间曝光的结果,并且将这些归一化的电化学电位分数相对于时间对数进行绘制。 通过绘制的数据将直线斜率的负值分为冷却水中测得的平均Co-60浓度,长期剂量率与该参数的标准曲线用于预测最终的长期 进行电化学电位测量的核电厂的辐射累积性能。

    Ultrafiltration circuit for the primary cooling fluid of a
pressurized-water nuclear reactor
    122.
    发明授权
    Ultrafiltration circuit for the primary cooling fluid of a pressurized-water nuclear reactor 失效
    用于加压水核反应堆初级冷却液的超滤电路

    公开(公告)号:US4699755A

    公开(公告)日:1987-10-13

    申请号:US867977

    申请日:1986-05-29

    摘要: Ultrafiltration circuit for the primary cooling fluid of a pressurized-water nuclear reactor, comprising a first loop (27) taken off from the discharge branch (10) of the volumetric and chemical monitoring circuit (8) and a second loop (28) taken off from the charge branch (11) of the circuit (8). Each of the loops (27, 28) incorporates an ultrafilter (30, 50). The concentrate from the ultrafilter (30) located on the first loop (27) is cooled, depressurized and conveyed into the chemical monitoring circuit (8) via a pipe (38) downstream of the main cooling and depressurizing device (12, 13) of the circuit (8). The concentrate from the ultrafilter (50) of the loop (28) is conveyed into the chemical monitoring circuit (98) via a pipe (58) upstream of the device (12, 13).

    摘要翻译: 用于加压 - 水核反应堆的主冷却流体的超滤电路,包括从容积和化学监测电路(8)的放电支路(10)取出的第一回路(27)和从第二回路(28)取出的第二回路 来自电路(8)的电荷分支(11)。 每个环路(27,28)都包含超滤器(30,50)。 来自位于第一回路(27)上的超滤器(30)的浓缩物被冷却,减压并通过主冷却和减压装置(12,13)下游的管道(38)输送到化学品监测回路(8) 电路(8)。 来自环路(28)的超滤器(50)的浓缩物通过设备(12,13)上游的管道(58)输送到化学监测回路(98)。

    Determining the difference between the temperature of a liquid flowing
in a closed system and its saturation temperature
    123.
    发明授权
    Determining the difference between the temperature of a liquid flowing in a closed system and its saturation temperature 失效
    确定在封闭系统中流动的液体的温度与其饱和温度之间的差异

    公开(公告)号:US4652251A

    公开(公告)日:1987-03-24

    申请号:US440905

    申请日:1982-11-12

    申请人: Bobby L. Day

    发明人: Bobby L. Day

    CPC分类号: G21C17/022 G01K3/08 G01N25/08

    摘要: A method of determining with improved accuracy, the temperature margin to saturation of a heated pressurized liquid or vapor contained in a closed system. This method is characterized by the utilization of a direct measurement of the pressure margin to saturation instead of a measurement of the actual pressure of the system. The actual temperature of the system is used to determine the appropriate portion of the saturation curve to be used for the conversion of the pressure margin to saturation to the temperature margin to saturation.

    摘要翻译: 一种以更精确的方式确定封闭系统中包含的加热的加压液体或蒸气的温度裕度。 该方法的特征在于利用将压力裕度直接测量到饱和,而不是对系统的实际压力的测量。 系统的实际温度用于确定用于将压力裕度转换为饱和度至饱和温度的饱和曲线的适当部分。

    Electrode for electrochemical measurements in aqueous solutions of high
temperatures
    124.
    发明授权
    Electrode for electrochemical measurements in aqueous solutions of high temperatures 失效
    用于在高温水溶液中进行电化学测量的电极

    公开(公告)号:US4636292A

    公开(公告)日:1987-01-13

    申请号:US729426

    申请日:1985-05-01

    CPC分类号: G21C17/022

    摘要: An electrode (20) for electrochemical measurements in aqueous solutions at high temperatures, especially measurements in water in or from a primary or secondary circuit of a nuclear reactor in operation at a temperature of the water substantially prevailing at that time, comprises a conductor (21) of a platinum-group metal which for part of its extension is enclosed within a casing (22) making tight contact with the conductor and consisting of sintered-together particles of aluminum oxide, zirconium oxide or other electrically-insulating material which is inert to water. The conductor has one part (21a) exposed the aqueous solution and one connection part (21b) for connection to an electrical measuring member.

    摘要翻译: 用于在高温下在水溶液中进行电化学测量的电极(20),特别是在当时基本上盛行的水的温度下操作的核反应堆的初级或次级回路中的水中的水中的测量值包括导体(21 的一部分铂族金属,其部分延伸部分被封闭在与导体紧密接触的壳体(22)内,并且由氧化铝,氧化锆或其它电绝缘材料的烧结在一起的颗粒组成,其对于 水。 导体具有暴露水溶液的一部分(21a)和用于连接到电测量部件的一个连接部分(21b)。

    Light water reactor primary coolant leakage monitor
    125.
    发明授权
    Light water reactor primary coolant leakage monitor 失效
    轻水反应器主要冷却液泄漏监测器

    公开(公告)号:US3849655A

    公开(公告)日:1974-11-19

    申请号:US31576372

    申请日:1972-12-15

    申请人: COMBUSTION ENG

    发明人: MARTUCCI J

    摘要: This invention consists of a method for the detection of leakage of a first fluid into a second fluid or into the surrounding atmospheric envelope. The first fluid is irradiated with high energy radiation to produce radionuclides which decay with the characteristic emission of angularly correlated radiations. One example of such a radionuclide is a positron emitter which decays with the emission of a positron which immediately annihilates with an electron. Two gamma photons are released from the positron-electron annihilation event and the gamma photons propagate in opposite directions. A sample of the second fluid is monitored by at least two scintillation detectors oriented to correspond with the characteristic angles of the angularly correlated radiations. The detectors are electrically connected to coincidence circuitry. Only those pairs of radiation emissions which simultaneously activate the angularly positioned scintillation detectors are registered on a counter.

    摘要翻译: 本发明包括一种用于检测第一流体泄漏到第二流体或周围大气环境中的方法。 用高能量辐射照射第一流体以产生放射性核素,其随着角度相关辐射的特征发射而衰减。 这种放射性核素的一个例子是正电子发射体,随着正电子的发射衰减,电子立即与电子消失。 两个伽马光子从正电子 - 电子湮灭事件中释放出来,伽马光子以相反的方向传播。 通过至少两个闪烁检测器监测第二流体的样品,其被定向成与角度相关辐射的特征角度相对应。 检测器电连接到符合电路。 只有那些同时激活角位置的闪烁检测器的辐射发射对才被记录在计数器上。

    Apparatus with flow assembly including temperature sensors and heating element

    公开(公告)号:US12062460B2

    公开(公告)日:2024-08-13

    申请号:US17535069

    申请日:2021-11-24

    摘要: The apparatus includes a flowmeter coupled a surface exposed to a flow channel. The flowmeter monitors a flow of coolant. The flowmeter includes a first temperature sensor that generates first temperature data based on measuring a first temperature of a first flowstream, a heating element coupled to the first temperature sensor where the heating element applies heat to the first temperature sensor through an interface, a second temperature sensor generates second temperature data based on measuring a second temperature of a second flowstream, the second temperature sensor being spaced apart from the heating element, and the second temperature sensor being at least partially insulated from the heating element so the second temperature data generated by the second temperature sensor is independent of heat generated by the heating element. A processor calculates a flowrate of the coolant based on the second temperature data and a temperature of the coolant fluid.