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公开(公告)号：US4544522A
公开(公告)日：1985-10-01
申请号：US409946
申请日：1982-08-20
CPC分类号： G21C3/3566 , Y02E30/40
摘要： A spacer for use in a fuel assembly of a nuclear reactor having thin, full-height divider members, slender spring members and laterally oriented rigid stops and wherein the total amount of spacer material, the amount of high neutron cross section material, the projected area of the spacer structure and changes in cross section area of the spacer structure are minimized whereby neutron absorption by the spacer and coolant flow resistance through the spacer are minimized.
摘要翻译： 用于具有薄的全高分隔构件，细长弹簧构件和横向定向的刚性挡块的核反应堆的燃料组件中的间隔件，其中间隔材料的总量，高中子截面材料的量，投影面积 并且间隔件结构的横截面面积的变化被最小化，使得间隔件的中子吸收和通过间隔件的冷却剂流动阻力最小化。
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公开(公告)号：US4383394A
公开(公告)日：1983-05-17
申请号：US220826
申请日：1980-12-29
IPC分类号： G21C23/00 , B23D45/20 , B23D57/00 , B28D1/04 , G01N1/04 , G01N33/00 , G21C17/00 , G21C19/02 , B23D45/02 , B23D47/02
CPC分类号： G21C17/00 , B23D57/0084 , B28D1/045 , G01N1/04 , G01N2033/0093 , Y10S83/919 , Y10S83/93 , Y10T83/05 , Y10T83/0596 , Y10T83/68 , Y10T83/7772
摘要： A remotely operable device for cutting sample pieces from the walls of an irradiated component while the component is submerged in a pool of water to shield the operator from radiation.
摘要翻译： 一种可远程操作的装置，用于在将部件浸没在水池中以从操作人员免受辐射而从被照射部件的壁上切割样品片。
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公开(公告)号：US4428903A
公开(公告)日：1984-01-31
申请号：US253090
申请日：1981-04-13
CPC分类号： G21C17/06 , Y10T29/49927 , Y10T29/49929
摘要： An arrangement for crimping a malleable sleeve over a hole in a punctured nuclear fuel rod in order to prevent the escape of fission gases into the external environment. The arrangement operates underwater and includes jaws for crimping the sleeve onto the fuel rod, which are operated by a hydraulic cylinder. The jaws crimp circumferential sealing ridges onto the inner surface of the sleeve, which bear against the fuel rod.
摘要翻译： 为了防止裂变气体逸出到外部环境中，用于将可延展的套筒压接在穿刺的核燃料棒的孔上的布置。 该装置在水下运行，并且包括用于将套筒压接到由液压缸操作的燃料棒上的钳口。 夹爪将周向密封脊部压紧到套筒的内表面上，该内表面承受燃料棒。
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公开(公告)号：US4374024A
公开(公告)日：1983-02-15
申请号：US234957
申请日：1981-02-17
CPC分类号： B05C17/00
摘要： An underwater suction device for collecting irradiated materials in a pool of water. The device includes injection and suction tubes and a removable, disposable filter for capturing irradiated materials. Pressurized water is injected into the suction tube through a jet pump nozzle to establish a suction flow through the tube. The suction device is manually positionable by an operator standing at a dry location and extending the device underwater by maneuvering a positioning pole. The pole is pivotally connected to the injection or suction tube by a variably positioning latching mechanism.
摘要翻译： 用于在水池中收集辐照材料的水下抽吸装置。 该装置包括注射和抽吸管和用于捕获辐射材料的可移除的一次性过滤器。 加压水通过喷射泵喷嘴注入吸管，以建立穿过管的吸力。 抽吸装置可以由站在干燥位置的操作者手动定位，并通过操纵定位杆将设备延伸到水下。 杆通过可变定位的锁定机构枢转地连接到注射或吸入管。
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公开(公告)号：US4145251A
公开(公告)日：1979-03-20
申请号：US805649
申请日：1977-06-13
申请人： Frank D. Qurnell
发明人： Frank D. Qurnell
CPC分类号： G21C17/00
摘要： Remotely manipulatable probe and apparatus for positioning a corrosion thickness sensing transducer over selected areas of the surface of a radioactive component submerged in a pool of water for radiation shielding. BACKGROUND In known types of nuclear power reactors, for example as used in the Dresden Nuclear Power Station near Chicago, Ill., the reactor core comprises a plurality of spaced fuel assemblies arranged in an array capable of self-sustained nuclear fission reaction. The core is contained in a pressure vessel wherein it is submerged in a working fluid, such as light water, which serves both as coolant and as a neutron moderator. Each fuel assembly comprises a removable tubular flow channel, typically of approximately square cross section, surrounding an array of elongated, cladded fuel elements or rods containing suitable fuel material, such as uranium or plutonium oxide, supported between upper and lower tie plates. The fuel assemblies are supported in spaced array in the pressure vessel between an upper core grid and a lower core support plate. The lower tie plate of each fuel assembly is formed with a nose piece which fits in a socket in the core support plate for communication with a pressurized coolant supply chamber. The nose piece is formed with openings through which the pressurized coolant flows upward through the fuel assembly flow channels to remove heat from the fuel elements. A typical fuel assembly of this type is shown, for example, by B. A. Smith et al. in U.S. Pat. No. 3,689,358. An example of a fuel element or rod is shown in U.S. Pat. No. 3,378,458. Additional information on nuclear power reactors may be found, for example, in "Nuclear Power Engineering", M. M. El-Wakil, McGraw-Hill Book Company, Inc., 1962. While the various reactor components are thoroughly factory tested before being placed in the reactor, there is a continuing need for in-service inspection equipment which can rapidly and conveniently verify the integrity of or detect any anomalies in such components at the reactor site, particularly after such components have been subjected to reactor service and have, therefore, become radioactive. Such radioactive condition of used components requires remotely operable equipment which can examine such components under water to protect the test equipment operators from radiation. A particular need is inspection equipment which can provide a nondestructive examination and quantitative indication of corrosion formation, such as oxide formation, on such reactor components. It is particularly desirable to provide corrosion measurement of removable reactor components which potentially have a relatively long service life such as fuel assembly flow channels. For example, as mentioned above, each fuel assembly is surrounded by a removable tubular flow channel. While the normal service life of a fuel assembly in the reactor core is in the order of four years, the flow channel can be removed and reused on a replacement fuel assembly in the absence of excessive corrosion or other defects. Previous methods of determining the extent of channel corrosion involved the cutting up of a channel and the shipping of samples of corroded portions to a laboratory for examination. This approach resulted in destruction of potentially reusable channels and an undesirable expenditure of time and money. Thus there is a need for remotely operable, nondestructive corrosion measuring equipment for determining whether or not a radiated component is fit for further service. Fuel assembly channels are normally formed of a zirconium alloy made up of two U-shaped members welded together. They are usually factory processed by autoclaving (exposure to high temperature steam) to form a thin, tight protective oxide surface film of deep gray or black color. In service oxide corrosion usually occurs at local areas, expecially at portions which have been exposed to highest temperatures and neutron flux density, and develops as clusters of pin point spots or nodules of corrosion which are light grey or white in color and which thus give the local area a "salt and pepper" appearance. As such corrosion progresses, the nodules expand in area and eventually coalesce to form a continuous oxide corrosion film or sheet over the local area. Continued corrosion results in a thickening of the oxide film and eventual spalling, that is, a flaking off of the oxide particles. Under present procedures, the channel is removed from service before spalling is expected to occur to avoid contamination of the coolant with the oxide particles. Measurement of thickness of the corrosion film can be used to preduct the onset of spalling. Measurement of corrosion thickness can also be used to indicate the effectiveness of heat treatment and other processes used to provide improved corrosion resistance. It is also desirable to examine other local areas of the channel such as weld seams, for indications of corrosion. Therefore it is an object of the invention to remotely and nondestructively measure formation of corrosion on a radioactive component. It is another object of the invention to provide a corrosion thickness sensing means which readily and remotely can be positioned over a selected area of a radioactive component. Equipment is commercially available which uses an eddy-current technique for indicating the distance between a transducer and a conductive surface. The transducer includes a coil which is energized by a high frequency current. Magnetic flux from the coil produces eddy currents in the conductive surface. Thus the power or energy supplied by the coil to produce the eddy currents is also proportional to the distance between the transducer and the conductive surface. This displacement dependent variation in power is detected by suitable electronic circuitry and converted to a calibrated display or recording of the distance between the transducer and the conductive surface. Thus such a device can be used to measure the thickness of a nonconductive coating on a metal. It is another object of the invention to utilize an eddy-current technique to remotely measure thickness of corrosion on the surface of radioactive components. SUMMARY These and other objects of the invention are achieved by a transducer containing probe, suspended at the end of a manually manipulatable pole, which can be visually positioned over selected areas of a radioactive component submerged to a suitable depth in shielding water. The probe comprises a body portion formed of a transparent material and having the general shape of a frustum of a cone, the transducer being resiliently supported in a central bore of this body portion. Since the body portion transmits light and refracts light at its conical surface, the operator can, in effect, see through and beneath the probe to position the transducer over the desired local area of the component being examined. In the illustrated embodiment, the body is surrounded by a ring of metal of sufficient weight to provide a desired force of the resiliently mounted transducer against the surface under examination.
摘要翻译： 远程可操纵探头和设备，用于将腐蚀厚度传感传感器定位在浸没在水池中的放射性元件表面的选定区域
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公开(公告)号：US4420455A
公开(公告)日：1983-12-13
申请号：US233841
申请日：1981-02-12
摘要： An amphibious end plug gauging device and method for determining the axial location of nuclear fuel element end plugs within or without the upper tie plate of a fuel bundle. The gauging device is maneuvered toward an underwater fuel bundle in a reactor service pool and its tip inserted in a preselected tie plate shank hole to engage the end of a fuel element in the bundle. The position of the fuel element relative the upper surface of the tie plate is registered on a dial indicator.
摘要翻译： 一种用于确定核燃料元件端塞在燃料束的上部连接板内部或之外的轴向位置的水陆两用端塞测量装置和方法。 测量装置在反应堆服务池中朝向水下燃料束操纵，其尖端插入预选的连接板柄孔中以与束中的燃料元件的端部接合。 燃料元件相对于连接板上表面的位置登记在刻度盘上。
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