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61. 发明申请

WO2012060563A2 원자력 발전소 냉각계통의 ｐＨ 측정을 위한 광섬유 프로브 및 이를 이용한 ｐＨ 측정 시스템 审中-公开
标题翻译：用于核电站冷却系统pH测量的光纤探头和使用它的pH测量系统
公开(公告)号：WO2012060563A2
公开(公告)日：2012-05-10
申请号：PCT/KR2011/007805
申请日：2011-10-19
申请人： 순천향대학교 산학협력단 , 박병기 , 이봉수 , 유욱재
发明人： 박병기 , 이봉수 , 유욱재
IPC分类号： G01N21/80 , G21C17/02
CPC分类号： G01N21/8507 , G01N21/80 , G21C17/022
摘要： 본 발명은 원자력 발전소 냉각계통의 pH 측정을 위한 광섬유 프로브 및 이를 이용한 pH 측정 시스템에 관한 것으로서, 더욱 상세하게는 유체 채널로 삽입되는 광섬유의 외주면을 보호튜브로 둘러싸고, 보호튜브로부터 노출되는 광섬유의 단부에 방수막을 형성한 후, 상기 방수막의 표면에 졸-겔(sol-gel)법으로 형성된 다공성의 pH 반응막을 구비함으로써 광섬유가 고온·고압의 유체에 직접 접촉되어 열화되는 것을 방지함과 동시에, 졸-겔법을 통해 형성된 다공성의 pH 반응막 내에 pH 반응물질을 함침시켜 사용함으로써 pH 반응물질의 열화를 효과적으로 방지할 수 있어 원자력 발전소의 냉각계통과 같이 고온·고압 환경 하에서의 유체의 pH를 정확하게 측정할 수 있는 원자력 발전소 냉각계통의 pH 측정을 위한 광섬유 프로브 및 이를 이용한 pH 측정 시스템에 관한 것이다. 본 발명에 따른 원자력 발전소 냉각계통의 pH 측정을 위한 광섬유 프로브는, 코어와 클래딩으로 이루어져 광을 전송하는 광섬유와; 상기 광섬유에서 유체 채널에 삽입되는 부분의 외주면을 둘러싸도록 형성되는 보호튜브와; 상기 보호튜브로부터 노출되는 광섬유의 단부에 연결되어, 상기 보호튜브의 내부를 밀폐시키는 방수막과; 상기 방수막 상부에 구비되며, 유체와 반응하여 유체의 pH에 따라 색상이 변화되는 pH 반응물질이 함침되어 있는 pH 반응막; 및 일측에 개방부가 형성된 중공형의 몸체로 형성되어, 상기 개방부를 통해 보호튜브에 둘러싸인 광섬유의 단부에 연결되며, 몸체에는 몸체 외부를 흐르는 유체를 몸체 내부로 유입시키기 위해 몸체를 가로지르며 관통하는 유입구가 형성되어 있는 캡;을 포함하여 구성되는 것을 특징으로 한다.
摘要翻译：
本发明涉及一种光纤探针，并使用用于核电站冷却体系的pH测量相同的pH值测量系统，并且更特别是围绕所述光纤的外周面插入到流体通道到所述保护管，水膜上的光纤端部形成从所述保护管，在表面上的水膜溶胶 - 通过具有形成于（溶胶 - 凝胶）处理膜纤维的凝胶多孔的pH值反应暴露后为高温＆middot;与所述高压流体直接接触防止降解，并在同一时间，溶胶 - 通过使用与通过凝胶方法，以防止pH值的反应物的降解形成的pH值响应膜的孔隙率范围内的pH值的反应性材料浸渍有效得到热＆middot作为核电厂的冷却系统;高压用于核电站冷却系统pH值测量的光纤探头，可精确测量环境中流体的pH值及其用途到pH测量系统。根据本发明的用于核电站冷却系统的pH测量的光纤探针包括：包括芯和包层并且透射光的光纤; 保护管，其形成为包围插入流体通道中的光纤的一部分的外周表面; 连接到从保护管暴露的光纤端部以密封保护管内部的防水膜; 一种pH反应膜，其设置在防水膜上，并浸渍有pH反应物质，该pH反应物质根据与流体反应的流体的pH而发生颜色变化; 并与中空开口部分的主体形成在一侧上形成，连接到所述端部穿过所述开口由保护管包围的光纤，所述主体具有穿过主体穿过，以引入流过身体外部到主体内的流体的入口还有一个帽子，上面盖着帽子。

62. 发明申请

WO2012029510A1 原子炉燃料健全性モニタ审中-公开
标题翻译：核反应堆燃料卫生监测
公开(公告)号：WO2012029510A1
公开(公告)日：2012-03-08
申请号：PCT/JP2011/068126
申请日：2011-08-09
申请人：三菱重工業株式会社 , 西村孝夫 , 木野健一郎
发明人：西村　孝夫 , 木野　健一郎
IPC分类号： G21C17/00 , G21C17/02 , G21C17/07
CPC分类号： G01T1/167 , G01T7/02 , G21C1/022 , G21C17/02 , G21C17/022 , G21C17/06
摘要：　作業員の人手を介さずに原子炉の冷却材又は溶存ガスが定期的にサンプル採取点から採取され、原子炉の冷却材又は溶存ガスに含まれる特定の放射性核種の濃度が測定可能な原子炉燃料健全性モニタを提供する。原子炉燃料健全性モニタは、原子炉の被測定媒体の特定放射性核種のγ線を検出するγ線検出器と、被測定媒体を内部に保持し、γ線検出器の周囲を取り囲むサンプル容器と、一定量の被測定媒体をサンプル容器に取り込む制御を行うと共にγ線検出器が検出した単位時間当たりのγ線データと、サンプル容器に取り込まれる被測定媒体の容積から特定放射性核種の濃度を算出する計測制御装置と、を有する。
摘要翻译：提供一种核反应堆燃料健康监测器，其能够通过在没有工人的情况下从样品提取点周期性地提取冷却剂或核反应堆的溶解气体来测量核反应堆的冷却剂或溶解气体中所含的特定放射性核素的浓度。核反应堆燃料健康监视器具有伽马射线检测器，其检测核反应堆要测量的介质的特定放射性核素的伽马射线，样品容器将待测介质包围在伽马射线检测器中，测量控制装置，其进行控制以将给定量的待测量介质取入样品容器，并计算由伽马射线检测器检测的每单位时间的伽马射线数据和特定放射性核素从介质体积的浓度到被测量进入样品容器。

63. 发明申请

WO2008093026A3 METHOD FOR ESTIMATING THE CONCENTRATION OF A CHEMICAL ELEMENT IN THE PRIMARY COOLANT OF A NUCLEAR REACTOR 审中-公开
标题翻译：估计核反应堆初级冷却液中化学元素浓度的方法
公开(公告)号：WO2008093026A3
公开(公告)日：2008-11-27
申请号：PCT/FR2007002155
申请日：2007-12-21
申请人： AREVA NP , VERNERET CLAUDE
发明人： VERNERET CLAUDE
IPC分类号： G21C17/022
CPC分类号： G21C17/022 , G21Y2002/204 , G21Y2004/40
摘要： The invention relates to a method for estimating the concentration (C) of a chemical element in the primary coolant of a nuclear reactor, in which said reactor includes means for injecting into the primary coolant a dilution solution or a concentrated solution of said chemical element at a predetermined concentration (C*), and a sensor capable of measuring a magnitude (Cm) representative of the concentration of said chemical element. The method is an iterative method that comprises repeatedly at each time step k: a step of acquiring the magnitudes (qdk) and (qck) representative of the injection flows of the dilution solution and the concentrated solution at step k, and a magnitude (Cmk) representative of the concentration measured by the sensor; the step of calculating an estimated value (Cek+1) of the concentration of said chemical element in the primary coolant at the step k+1 based on the representative values (qdk, qck, Cmk) acquired at step k.
摘要翻译：本发明涉及一种用于估计核反应堆的主要冷却剂中的化学元素的浓度（C）的方法，其中所述反应器包括用于将稀释溶液或所述化学元素的浓缩溶液注入到主冷却剂中的装置预定浓度（C *）和能够测量表示所述化学元素浓度的量值（Cm）的传感器。该方法是在每个时间步骤k处重复地重复的迭代方法：获取代表在步骤k的稀释溶液和浓缩溶液的注入流量的量级（qdk）和（qck）的步骤，以及幅度（Cmk ）表示由传感器测量的浓度; 基于在步骤k获取的代表值（qdk，qck，Cmk），计算步骤k + 1中的一次冷却剂中的所述化学元素的浓度的估计值（Cek + 1）的步骤。

64. 发明申请

WO0197232A3 METHOD AND APPARATUS FOR AUTOMATED CRACK BEHAVIOR PREDICTION DETERMINATION 审中-公开
标题翻译：自动裂纹行为预测法的方法与装置
公开(公告)号：WO0197232A3
公开(公告)日：2002-04-18
申请号：PCT/US0118300
申请日：2001-06-06
申请人： GEN ELECTRIC
发明人： HORN RONALD MARTIN , FORD FRANCIS PETER , ANDRESEN PETER LOUIS , MUI JENNY Y
IPC分类号： G21C17/003 , G21C17/00 , G21C17/022 , G21D3/04
CPC分类号： G21C17/0225 , G21C17/022 , G21Y2002/104 , G21Y2002/502 , G21Y2004/401
摘要： A method of predicting component crack behavior in a nuclear reactor provides access to a crack growth behavior model (16) over a global network (252). A user inputs water chemistry and material characteristics of a particular nuclear reactor and can perform crack growth rate predictions by accessing the behavior model over the computer network. A crack growth prediction profile or crack growth based result is output over the network according to an analysis by the behavior model.
摘要翻译：预测核反应堆中的部件裂纹行为的方法提供了通过全局网络访问裂纹生长行为模型（16）（252）。用户输入特定核反应堆的水化学和材料特性，并可以通过访问计算机网络上的行为模型来执行裂纹扩展速率预测。根据行为模型的分析，通过网络输出裂纹扩展预测曲线或基于裂纹增长的结果。

65. 发明专利

TW245765B 催化反應器套失效
简体标题：催化反应器套
公开(公告)号：TW245765B
公开(公告)日：1995-04-21
申请号：TW082110331
申请日：1993-12-07
申请人：奇異電器公司
发明人：吉拉德.馬隆.高登 , 貝絲.安.馬克里斯特 , 詹姆士.艾德華.契恩利 , 詹姆士.霍華德.特胡尼
IPC分类号： F16L
CPC分类号： G21C17/0225 , B01J35/04 , G21C17/022 , G21Y2002/103 , G21Y2004/10 , G21Y2004/304
摘要：一種催化重組裝置，用以使具有稀釋濃度成流體並以高溫在管道(50)中流動之二或多分子種發生反應。此類分子種在大量之流體中性質穩定，但因具高電化學潛力而在管壁上容易造成應力蝕裂。若該管路，如同在核能電廠中，形成冷卻系統之一部分，則分解後之化學種便流佈在整個系統中而有不良後果，為降低此種電化學潛力，便在要防止應力蝕裂之組件之上游加裝具有催化表面之套子（66，80）。該套子之催化表面便形成小量之良性反應產品（例如水），因而降低不良化學種之濃度。在各類鍵處有精巧之催化重組器存在便會大大降低電化學潛力，並使管路及容器與接到管路之內部機構受到保護而免於腐蝕侵襲。
简体摘要：一种催化重组设备，用以使具有稀释浓度成流体并以高温在管道(50)中流动之二或多分子种发生反应。此类分子种在大量之流体中性质稳定，但因具高电化学潜力而在管壁上容易造成应力蚀裂。若该管路，如同在核能电厂中，形成冷却系统之一部分，则分解后之化学种便流布在整个系统中而有不良后果，为降低此种电化学潜力，便在要防止应力蚀裂之组件之上游加装具有催化表面之套子（66，80）。该套子之催化表面便形成小量之良性反应产品（例如水），因而降低不良化学种之浓度。在各类键处有精巧之催化重组器存在便会大大降低电化学潜力，并使管路及容器与接到管路之内部机构受到保护而免于腐蚀侵袭。

66. 发明公开

US20240296966A1 METHOD FOR THERMAL PERFORMANCE MONITORING OF A NUCLEAR POWER PLANT USING THE NCV METHOD 审中-公开
公开(公告)号：US20240296966A1
公开(公告)日：2024-09-05
申请号：US18444473
申请日：2024-02-16
申请人： Fred Donald Lang
发明人： Fred Donald Lang
IPC分类号： G21C17/032 , G21C7/32 , G21C17/022
CPC分类号： G21C17/032 , G21C7/32 , G21C17/022
摘要： This invention relates to the monitoring and diagnosing of nuclear power plants for its thermal performance using the NCV Method. Its applicability comprises any nuclear reactor such as used for research producing a useful output. Its greatest applicability lies with conventional Pressurized Water Reactor and Boiling Water Reactor nuclear plants generating an electric power. Its teachings of treating fission as an inertial process, a phenomena which is self-contained following incident neutron capture, allows the determination of an absolute neutron flux. This process is best treated by Second Law principles producing a total fission exergy. This invention also applies to the design of fusion thermal systems regards the determination of its Second Law viability and absolute plasma flux.

67. 发明公开

US20240282473A1 METHOD FOR ONLINE RADIOISOTOPE MEASUREMENT FOR FAILED FUEL CHARACTERIZATION IN PRIMARY SODIUM SYSTEMS 审中-公开
公开(公告)号：US20240282473A1
公开(公告)日：2024-08-22
申请号：US18393377
申请日：2023-12-21
申请人： TerraPower, LLC
发明人： Jesse R. Cheatham, III , Christopher M. Reagan , John E. Truax , Jacob Wilcox
IPC分类号： G21C17/022 , G21C17/00
CPC分类号： G21C17/022 , G21C17/002
摘要： A failed fuel pin emits cesium into the primary sodium coolant and xenon into the cover gas in a reactor vessel. A pipe containing radioactive liquid sodium accepts flowing primary sodium from the reactor vessel. A radiation detector is positioned adjacent the pipe such that gamma radiation emitted from the pipe can be measured. The pipe may be isolated to increase detection limits by allowing short-lived isotopes to decay. The isotopic ratio of 137Cs/134Cs can be measured, which can be used to determine the burnup of a fuel assembly from within the core, and therefore, the failed fuel assembly can be identified based at least in part on the burnup. Further, mass spectrometry may be used to measure the ratio of a stable and unstable xenon isotope. The identification techniques may be used in conjunction to quickly identify a failed fuel assembly in-situ and during reactor operation.

68. 发明授权

US09779841B2 Process for the accurate characterization of low level nuclear waste 有权
公开(公告)号：US09779841B2
公开(公告)日：2017-10-03
申请号：US14186536
申请日：2014-02-21
申请人： David W James , Tom Kalinowski
发明人： David W James , Tom Kalinowski
IPC分类号： G21C17/022 , G21C17/00 , G21F9/12 , G21C19/307
CPC分类号： G21C17/002 , G21C17/022 , G21C19/307 , G21F9/12
摘要： A method of determining and quantifying the presence and concentration of regulated radionuclides present in filter material used to remove radionuclide contaminants from the cooling water of a nuclear reactor. Multiple samples of the reactor cooling water are taken and the presence and concentration of directly measurable fission and activation produced radionuclides are determined through gamma spectroscopy. The release rate of radioactivity from the reactor as a function of the removal rate of the filter material is determined at equilibrium. The presence and the concentration of the indirectly measured fission regulated radionuclides are determined as a function of release rates of the directly measurable fission produced isotopes.

69. 发明申请

US20170176315A1 METHOD OF EVALUATING AMOUNT OF FOREIGN MATTER PASSED THROUGH RECIRCULATION SUMP SCREEN 审中-公开
公开(公告)号：US20170176315A1
公开(公告)日：2017-06-22
申请号：US15375346
申请日：2016-12-12
申请人： Mitsubishi Heavy Industries, Ltd.
发明人： Hideyuki Sakata , Hiroyuki Kojima , Hiroshi Matsuoka , Yuji Momose
IPC分类号： G01N15/08 , G21C15/18
CPC分类号： G01N15/0806 , G01N2015/084 , G21C15/182 , G21C17/022 , G21C19/307 , Y02E30/40
摘要： Acquiring sets of test data on amounts of foreign matter passed through a recirculation sump screen when different amounts of foreign matter are input; forming a passed foreign matter amount approximate line that approximates the amounts of passed foreign matter with respect to the amounts of input foreign matter on the basis of the sets of test data on the amounts of passed foreign matter; forming a passed foreign matter amount envelope tangent to the passed foreign matter amount approximate line; and estimating a total passed foreign matter amount with respect to the amounts of input foreign matter on the basis of the passed foreign matter amount envelope to evaluate the recirculation sump screen are provided.

70. 发明授权

US09322487B2 Nuclear grade air accumulation, indication and venting device 有权
标题翻译：核级空气积聚，指示和排气装置
公开(公告)号：US09322487B2
公开(公告)日：2016-04-26
申请号：US14358941
申请日：2012-11-16
申请人： Nuccorp, Inc.
发明人： Willie Turner Wood, Jr.
IPC分类号： F16K24/04 , G21C17/022 , G21C19/28 , F16K37/00 , G21D1/02
CPC分类号： F16K24/044 , F16K37/00 , G21C17/022 , G21C19/28 , G21D1/02 , Y02E30/40 , Y10T137/3099 , Y10T137/8342
摘要： A device for accumulating, isolating, indicating and venting accumulated gas in a fluid system pipe includes a main pipe fitting affixed to a system pipe in which a hole has been drilled. A standpipe attached to the pipe fitting houses a magnetic float. A magnetic-float level indicator exterior to the pipe indicates the magnetic float's level. A valve attached to the standpipe above the magnetic float allows controlled ventilation of the gas in the standpipe and thus in the piping system. Gas from the system pipe accumulates in the standpipe, removed from the primary fluid flow path of the system pipe. In the standpipe, as the liquid/gas interface drops, the float drops to a pre-determined level, at which point the user vents the gas from the piping system, causing the magnetic float to rise indicating that gas is again at acceptable levels in the piping system.
摘要翻译：用于在流体系统管道中积聚，分离，指示和排出积聚的气体的装置包括：固定到其中钻有孔的系统管道的主管件。连接到管件的立管装有一个磁浮子。管子外侧的磁浮液位指示器表示磁浮子的水平面。安装在磁浮子上方的立管的阀允许管道中的气体和管道系统中的气体受到控制的通风。来自系统管道的气体积聚在立管中，从系统管道的主要流体流动路径中移除。在立管中，当液体/气体界面下降时，浮子下降到预定的水平，此时用户从管道系统排出气体，导致磁性浮子上升，表明气体再次处于可接受的水平管道系统。

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