公开(公告)号：US20220392654A1

公开(公告)日：2022-12-08

申请号：US17891437

申请日：2022-08-19

申请人： BWXT Nuclear Energy Canada Inc.

发明人： Thomas G. Onderwater

IPC分类号： G21C17/04 ,  G21C17/00 ,  G21C17/07 ,  G21C17/10

摘要： A defective fuel bundle location system for use with a heavy water moderated nuclear fission reactor having a fueling machine, including a test tool defining an internal volume, the test tool being configured to be received within both the fueling machine and a corresponding fuel channel of the reactor, and a test container defining an internal volume, wherein the test container is configured to be received within the internal volume of the test tool and the internal volume of the test container is configured to receive primary fluid from the reactor when the test tool is disposed within the corresponding fuel channel of the reactor.

公开(公告)号：US11355254B2

公开(公告)日：2022-06-07

申请号：US16485057

申请日：2018-02-14

申请人： FRAMATOME

发明人： Franck Coustourier ,  Serge Roillet

IPC分类号： G21C17/07 ,  G21C19/07

摘要： A leakage testing device for testing leakage of a nuclear fuel assembly (18) by sipping. The device includes a collection assembly (32) that is configured to close an upper end (24A) of a cell (24) of a storage rack (22) for storing nuclear fuel assemblies discharged from a nuclear reactor (4). The closing prevents water contained in the cell from escaping via the upper end of the cell. The collection assembly is configured to collect products containing possible fission products released by a nuclear fuel assembly contained in the cell.

公开(公告)号：US20180010979A1

公开(公告)日：2018-01-11

申请号：US15535876

申请日：2015-12-07

申请人： AREVA GmbH

发明人： Wolfgang HUMMEL

IPC分类号： G01M3/20 ,  G21C17/07 ,  G21C19/07

CPC分类号： G01M3/205 ,  G21C17/07 ,  G21C19/07

摘要： The invention relates to a device for performing a leak test on a fuel rod capsule, which contains at least one fuel rod and test gas, which device comprises a test container, which is designed to accommodate at least one fuel rod capsule and can be lowered into a pool of a nuclear plant flooded with water. According to the invention, a mass spectrometer is fluidically connected to the interior of the test container in such a way that a gas flow can be fed to the mass spectrometer in order to sense the concentration of the test gas that has diffused into the test container from the fuel rod capsule.

公开(公告)号：US20170032854A1

公开(公告)日：2017-02-02

申请号：US15104971

申请日：2015-01-16

申请人： DOMINION ENGINEERING, INC.

发明人： David ARGUELLES ,  Robert D. VARRIN, JR.

IPC分类号： G21C17/07

CPC分类号： G21C17/07

摘要： A method and system detects failures in nuclear fuel assemblies (600). A water treatment device degasses/removes fission gases from water used in the canister (500) of a vacuum sipping device (30). A sipping procedure then detects a failure in a fuel assembly in the canister. The degassing improves a signal-to-noise ratio of the detector used during the sipping process, and improves the failure detection sensitivity of the system. Additionally and/or alternatively, gas may be recirculated through the canister water before the vacuum is applied so that fission gas concentration in the recirculating gas reaches a baseline equilibrium with the canister water. The vacuum is thereafter applied and the sipping procedure proceeds such that an increase in detected radioactivity over the baseline equilibrium indicates a leak in the fuel assembly.

摘要翻译： 一种方法和系统检测核燃料组件中的故障（600）。 水处理装置从真空吸取装置（30）的罐（500）中使用的水中除去/除去裂变气体。 然后，浸渍过程检测罐中的燃料组件中的故障。 脱气提高了在浸渍过程中使用的检测器的信噪比，并提高了系统的故障检测灵敏度。 另外和/或替代地，在施加真空之前，气体可以通过罐水再循环，使得再循环气体中的裂变气体浓度达到与罐水的基线平衡。 然后施加真空并且进行浸渍过程，使得检测到的放射性在基线平衡上的增加表示燃料组件中的泄漏。

公开(公告)号：US5516401A

公开(公告)日：1996-05-14

申请号：US271470

申请日：1994-07-07

申请人： Pierre Guillermier ,  Alain Blocquel

发明人： Pierre Guillermier ,  Alain Blocquel

IPC分类号： B23H3/08 ,  G21C17/07 ,  G21C19/02 ,  B23H3/10 ,  B23H9/00

CPC分类号： G21C19/02 ,  B23H3/08 ,  G21C17/07 ,  G21Y2002/402 ,  G21Y2004/501

摘要： An electrolyte is circulated between the surface to be machined, raised to an anode potential, and a tool electrode (9') raised to a cathode potential. The electrolyte contains lithium nitrate as a unique active product with a concentration of between 20 g/l and 2350 g/l and preferably between 50 g/l and 250 g/l. The process can be applied to the machining of the surface of any metallic component and in particular to the machining of the internal surface of tubular components (5) such as penetrations in the vessel bottom or closure head of a nuclear reactor; in this case the electrochemical machining cell consists of a cylindrical tool electrode (9') placed inside the component to be machined.

摘要翻译： 电解质在待加工表面之间循环，升高至阳极电位，并将工具电极（9'）升高至阴极电位。 电解液含有浓度为20g / l至2350g / l，优选为50g / l至250g / l的独特活性产物的硝酸锂。 该方法可以应用于任何金属部件的表面的加工，特别是加工管状部件（5）的内表面，例如在核反应堆的容器底部或封闭头中的穿透; 在这种情况下，电化学加工单元由放置在待加工部件内的圆柱形工具电极（9'）组成。

公开(公告)号：US5457720A

公开(公告)日：1995-10-10

申请号：US228526

申请日：1994-04-15

申请人： Dane T. Snyder ,  Raymond L. Armstrong

发明人： Dane T. Snyder ,  Raymond L. Armstrong

IPC分类号： G01N25/18 ,  B01D15/08 ,  B01D53/04 ,  G01N27/18 ,  G01N30/02 ,  G01N30/12 ,  G01N30/62 ,  G01N30/66 ,  G01N30/78 ,  G01T1/167 ,  G01T7/02 ,  G21C17/07 ,  G21C17/00

CPC分类号： G01N30/62 ,  G21C17/07 ,  G01N2030/025 ,  G01N2030/121 ,  G01N2030/626 ,  G01N2030/77 ,  G01N30/66 ,  G01N30/78 ,  G21Y2002/202 ,  G21Y2004/30 ,  G21Y2004/40

摘要： A process and system for the rapid concentration, separation and measurement of Kr-85 and Xe-133. By measuring the amount of Kr-85 radioisotope which is present, false positive signals for the vacuum sipping process can be eliminated. The fission gases are trapped by passing the recirculating gas stream through an adsorbing media. During this process, a known mixture of nonradioactive krypton and xenon is added to the gas stream which enters a thermal conductivity (TC) detector to calibrate the latter. The trapped gases are desorbed and injected into the inlet of a separating column. The column discharges into the TC detector. The TC detector discharge is diverted for counting to an evacuated beta detector chamber during the time that krypton is sensed by the TC detector. Any minute amount of Kr-85 is captured in the chamber, free of Xe-133. The detector discharge is diverted for counting to another evacuated beta detector chamber during the time that xenon is sensed by the TC detector. Any minute amount of Xe-133 is captured in the chamber, free of Kr-85.

摘要翻译： 用于快速浓缩，分离和测量Kr-85和Xe-133的方法和系统。 通过测量存在的Kr-85放射性同位素的量，可以消除真空吸收过程的假阳性信号。 裂解气体通过使再循环气流通过吸附介质而被捕获。 在此过程中，将已知的非放射性氪和氙混合物加入到进入热导率（TC）检测器以校准后者的气流中。 被捕获的气体被解吸并注入分离塔的入口。 该列排放到TC检测器中。 TC检测器放电在TC检测器感测氪时间内转向计数到抽空的β检测器室。 在室内捕获任何微量的Kr-85，不含Xe-133。 在TC检测器感测到氙时，检测器放电被转移到另一个抽空的β检测器室。 在室内捕获少量的Xe-133，不含Kr-85。

公开(公告)号：US5164149A

公开(公告)日：1992-11-17

申请号：US745357

申请日：1991-08-15

申请人： Masaki Katagiri

发明人： Masaki Katagiri

IPC分类号： G21C17/07 ,  G01T1/20 ,  G01T1/36 ,  G01T7/06

CPC分类号： G01T7/06

摘要： The present invention is directed to a nuclide separation precipitator system in which noble gas nuclear fission products are introduced into a gas reservoir and generate charged daughter nuclides in the gas reservoir. A collector collects three detectable charged daughter nuclides. A detector detects the energy distributions of beta-rays and gamma-rays emitted from the daughter nuclides collected in the collector and outputs signals indicative of the detected beta-rays and gamma-rays. Three pulse height discriminators discriminate the signals output from the detector into three respective energy levels of a low energy range, a middle energy range, and a high energy range. A first order simultaneous equation of three unknowns obtained by utilizing a fact that counting ratios of the three energy ranges vary for each daughter nuclide is then solved.

摘要翻译： 本发明涉及一种氮化物分离沉淀器系统，其中惰性气体核裂变产物被引入气藏并在气藏中产生带电荷的子核素。 收集器收集三个可检测的带电荷的子核素。 检测器检测从收集器收集的子核中发射的β射线和γ射线的能量分布，并输出指示检测到的β射线和γ射线的信号。 三个脉冲高度鉴别器将从检测器输出的信号区分为低能量范围，中等能量范围和高能量范围的三个相应的能级。 然后解决通过利用三个能量范围的计数比对于每个子核素变化的事实获得的三个未知数的一阶联立方程。

公开(公告)号：US4560529A

公开(公告)日：1985-12-24

申请号：US462852

申请日：1983-02-01

申请人： Richard P. Colburn

发明人： Richard P. Colburn

IPC分类号： G21C17/07 ,  G21C17/04 ,  G21C17/00

CPC分类号： G21C17/04

摘要： A system for detecting grossly failed reactor fuel by detection of particulate matter as accumulated on a filter.

摘要翻译： 通过检测积聚在过滤器上的颗粒物质来检测反应堆燃料总体失效的系统。

公开(公告)号：US4495143A

公开(公告)日：1985-01-22

申请号：US535462

申请日：1983-09-26

申请人： Kenny C. Gross ,  Matthew T. Laug

发明人： Kenny C. Gross ,  Matthew T. Laug

IPC分类号： G21C17/07 ,  G21C17/04

CPC分类号： G21C17/048

摘要： The invention discloses the use of stable isotopes of neon and argon, that are grouped in preselected different ratios one to the other and are then sealed as tags in different cladded nuclear fuel elements to be used in a liquid metal fast breeder reactor. Failure of the cladding of any fuel element allows fission gases generated in the reaction and these tag isotopes to escape and to combine with the cover gas held in the reactor over the fuel elements. The isotopes specifically are Ne.sup.20, Ne.sup.21 and Ne.sup.22 of neon and Ar.sup.36, Ar.sup.38 and Ar.sup.40 of argon, and the cover gas is helium. Serially connected cryogenically operated charcoal beds are used to clean the cover gas and to separate out the tags. The first or cover gas cleanup bed is held between approximately 0.degree. and -25.degree. C. operable to remove the fission gases from the cover gas and tags and the second or tag recovery system bed is held between approximately -170.degree. and -185.degree. C. operable to isolate the tags from the cover gas. Spectrometric analysis further is used to identify the specific tags that are recovered, and thus the specific leaking fuel element. By cataloging the fuel element tags to the location of the fuel elements in the reactor, the location of the leaking fuel element can then be specifically determined.

摘要翻译： 本发明公开了使用氖气和氩气的稳定同位素，其以预先选定的不同比率彼此分组，然后作为用于液态金属快速增殖反应器中的不同包层核燃料元件中的标签密封。 任何燃料元件的包层失效都能使反应中产生的裂变气体和这些标记同位素逸出并与保持在反应器中的覆盖气体结合在燃料元件上。 同位素特别是氖的Ne20，Ne21和Ne22，氩的Ar36，Ar38和Ar40，盖气是氦。 使用串联的低温操作木炭床清洁盖气并分离标签。 第一或覆盖气体净化床保持在约0°至-25°C之间，可操作以从覆盖气体和标签中除去裂变气体，第二或标签回收系统床保持在约-170°至-185° C.可操作地将标签与覆盖气体隔离。 光谱分析进一步用于识别回收的特定标签，从而识别特定的泄漏燃料元件。 通过将燃料元件标签分类到反应器中的燃料元件的位置，则可以具体确定泄漏的燃料元件的位置。

公开(公告)号：US4382906A

公开(公告)日：1983-05-10

申请号：US174171

申请日：1980-07-31

申请人： Rainer Ambros ,  Gottfried Paffrath

发明人： Rainer Ambros ,  Gottfried Paffrath

IPC分类号： G21C17/07 ,  G21C17/00

CPC分类号： G21C17/07

摘要： Nuclear fuel elements or slugs are removed from the nuclear reactor cores and subjected to inspection, according to the invention, by introducing a plurality of such elements into a submerged inspection vessel which is then closed, the liquid driven out by compressed air and deionized water (deionate) circulated through the inspection vessel at a constant rate. A portion of the deionized water is branched from the circulating stream at a constant rate and the activity of at least one fission-product nuclide is determined continuously to plot the activity versus temperature, thereby signaling a possible defect in the shell of a fuel element. In addition, ultrasonic vibration is applied in the inspection vessel to the fuel elements so that deposits on the exterior thereof are released into the deionate whose circulating path includes a filter and an ion-exchange column for removal of such deposits.

摘要翻译： 根据本发明，将核燃料元件或s塞从核反应堆堆芯中取出并进行检查，通过将多个这样的元件引入浸没的检查容器中，然后将其关闭，液体由压缩空气和去离子水（ 爱好者）以恒定的速率循环通过检验船。 去离子水的一部分以恒定速率从循环流中分支，连续测定至少一个裂变产物核素的活性以绘制活性与温度的关系，从而发出燃料元件外壳中的可能缺陷。 此外，在检查容器中将超声波振动施加到燃料元件，使得其外部的沉积物被释放到循环路径包括过滤器和用于除去这些沉积物的离子交换柱的酸性物质中。