-
公开(公告)号：US5600685A
公开(公告)日：1997-02-04
申请号：US427543
申请日：1995-04-24
IPC分类号： G21C19/105 , G21C19/00
CPC分类号： G21C19/105 , G21Y2002/201 , G21Y2002/304 , G21Y2002/402 , G21Y2004/305 , G21Y2004/401 , G21Y2004/501
摘要： An unlatching tool which can be used to uncouple and grapple standard handle and extended handle control rods from their associated control rod drives. The unlatching tool is lowered onto the handle of a control rod residing in the reactor core. Due to differences in the shapes of the handles of the standard handle and extended handle control rods, the tool is able to sense the type of control rod present and, through the use of a pneumatically actuated cylinder, position the unlatching mechanism at the appropriate elevation. In particular, a four-way valve, that is actuated by contact with the top corner of the handle of the extended handle control rod and is not contacted by the handle of the standard handle control rod, is used to differentiate between control rod types. The unlatching mechanism is positioned relative to the unlocking handle on the control rod using a pneumatic cylinder activated by the four-way valve. The cylinder has a stroke length equal to the difference in length between the standard handle and extended handle control rods.
摘要翻译： 一种解锁工具，可用于从相关的控制杆驱动器上拆下并抓住标准把手和扩展的手柄控制杆。 解锁工具下降到位于反应堆芯中的控制棒的手柄上。 由于标准手柄和扩展的手柄控制杆的把手形状不同，工具能够感测到存在的控制杆的类型，并且通过使用气动缸，将解锁机构定位在适当的高度 。 特别地，通过与伸出的手柄控制杆的手柄的顶角接触而不与标准手柄控制杆的手柄接触的四通阀用于区分控制杆类型。 使用由四通阀启动的气动缸，解锁机构相对于控制杆上的解锁把手定位。 气缸的行程长度等于标准把手和扩展手柄控制杆之间的长度差。
-
公开(公告)号：US4676948A
公开(公告)日：1987-06-30
申请号：US764677
申请日：1985-08-12
申请人： James E. Cearley , Kenneth R. Izzo
发明人： James E. Cearley , Kenneth R. Izzo
CPC分类号： G21C7/113 , G21Y2002/103 , G21Y2002/201 , G21Y2004/10 , G21Y2004/30 , Y02E30/39
摘要： A control rod for a nuclear reactor wherein plates of neutron absorbing material (e.g. hafnium) are used in the upper portion thereof and tubes containing a different neutron absorbing material (e.g. boron) are positioned beneath the plates. To relieve the tubes of the weight of the plates, the plates are attached to support members of the control rod frame, to prevent or reduce the area of a gap between the plates and the tubes, joints therebetween are provided.
摘要翻译： 用于核反应堆的控制棒，其中在其上部使用中子吸收材料（例如铪）板，并且将含有不同中子吸收材料（例如硼）的管定位在板下方。 为了减轻板的重量，板被附接到控制杆框架的支撑构件上，以防止或减小板和管之间的间隙的面积，提供它们之间的接合。
-
3.发明授权Method and apparatus for in situ detection of defective nuclear fuel assembly 失效用于原位检测有缺陷的核燃料组件的方法和装置
公开(公告)号：US5544208A
公开(公告)日：1996-08-06
申请号：US309383
申请日：1994-09-20
申请人： Hsueh-Wen Pao , David L. Faulstich , Dane T. Snyder , Johnny T. Ma , Kenneth R. Izzo , Joel C. Swanson , Martin S. Laurent , Peter F. Kachel
发明人： Hsueh-Wen Pao , David L. Faulstich , Dane T. Snyder , Johnny T. Ma , Kenneth R. Izzo , Joel C. Swanson , Martin S. Laurent , Peter F. Kachel
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 a system for detecting defective nuclear fuel assemblies in situ. The system includes two basic subsystems. The first subsystem is a sample collection system consisting of a hood placed over the fuel. A technique whereby a vacuum is drawn across a submerged nozzle of a degas tank is used to draw up the sample of fluid out of a fuel assembly. The second subsystem determines the amount of Kr-85 radioisotope contained in the fluid sample. This information is used to determine whether the fuel assembly contains a defective, i.e., leaking, fuel rod. The measurement values for Kr-85 in the fluid sample extracted from the fuel assembly are compared to the measurement values for Kr-85 in fluid samples taken from the reactor pool prior to fuel assembly testing and fluid samples taken from non-leaking control cells, the latter values representing the background to which the subject fuel assembly is compared. Based on this comparison, a determination is made concerning whether the subject fuel assembly is defective.
摘要翻译： 一种原位检测有缺陷的核燃料组件的方法和系统。 该系统包括两个基本子系统。 第一个子系统是一个样品收集系统，包括放置在燃料上的发动机罩。 使用通过脱气罐的浸没喷嘴抽取真空的技术来将流体样品从燃料组件中抽出。 第二个子系统确定流体样品中所含的Kr-85放射性同位素的量。 该信息用于确定燃料组件是否包含有缺陷的，即泄漏的燃料棒。 将从燃料组件提取的流体样品中的Kr-85的测量值与在燃料组装测试之前从反应池中获取的流体样品中的Kr-85的测量值和从非泄漏的控制电池获取的流体样品进行比较， 后一个值表示对象燃料组件与之比较的背景。 基于该比较，确定主体燃料组件是否有缺陷。
-
公开(公告)号：US4853176A
公开(公告)日：1989-08-01
申请号：US215188
申请日：1988-07-05
CPC分类号： G21C7/10 , G21Y2002/104 , G21Y2004/10 , G21Y2004/301 , G21Y2004/40 , Y02E30/39 , Y10S376/90
摘要： In a control rod construction for moderating and controlling a reaction of a nuclear reactor, a control rod structure is disclosed in which hafnium is welded to stainless steel. Typically, the control rod is confined for movement axially along its length into and out of the reactor. The hafnium is surrounded in the control rod structure by a sheath of stainless steel to inhibit movement relative to the control rod structure other than in the axial direction of control rod movement. The hafnium is friction welded to the stainless steel of the control rod so as to stress the weld in either tension or compression due to dynamic loading occurring from control rod movement. The stainless steel to which the hafnium is welded is in turn conventionally welded or mechanically connected to the remaining steel components of the control rod. There results a secure control rod structure having welded hafnium that can withstand the dynamic loadings of fast insertion of control rods such as those loadings which commonly occur under rapid control rod acceleration and deceleration due to SCRAM of a reactor.
-
公开(公告)号：US4512179A
公开(公告)日：1985-04-23
申请号：US546739
申请日：1983-10-28
申请人： Don G. Umble , Tsi-Pin Choong , Kenneth R. Izzo , Charles E. Burdg , Gary H. Hankin , Charles A. Dalke
发明人： Don G. Umble , Tsi-Pin Choong , Kenneth R. Izzo , Charles E. Burdg , Gary H. Hankin , Charles A. Dalke
IPC分类号： G01L27/00
CPC分类号： G01L27/005
摘要： A microprocessor controls pressure transducer testing, calibration, and adjustment. A transducer or unit under test (UUT) receives a fluid pressure signal from a test line, and outputs a corresponding electrical signal. A test pressure is output from a fluid pressure module which is connected to the UUT. A human operator is interrogated by the microprocessor based control unit as to (1) identifying details about the desired pressure UUT to be tested, and (2) the anticipated electrical range to be encountered in reply to an applied test pressure. The microprocessor then sequentially generates electrical output signals which are sent to the test lines to generate the test pressure pulses from a fluid pressure supply. The pressure test pulses are delivered to the UUT. As the UUT receives the sequence of pressure test pulses, the microprocessor records the output electrical signals generated by the UUT, and compares them to an internal reference pressure transducer output. Display of the results occurs with preferably the percent error calculated at each step. Provision for pressure transducer UUT calibration is made by providing the calibration instrument with the ability to issue tonal and visual signals in response to UUT adjustments, thus providing sense and amount of adjustments of the zero point and span range of the transducer under test.
摘要翻译： 微处理器控制压力传感器测试，校准和调整。 传感器或被测单元（UUT）从测试线接收流体压力信号，并输出相应的电信号。 从连接到UUT的流体压力模块输出测试压力。 操作人员由基于微处理器的控制单元进行询问，以便（1）识别关于要测试的所需压力UUT的细节，以及（2）应答应用的测试压力时遇到的预期电气范围。 然后微处理器顺序地产生电输出信号，其被发送到测试线以从流体压力源产生测试压力脉冲。 压力测试脉冲被传送到UUT。 当UUT接收到压力测试脉冲序列时，微处理器记录由UUT产生的输出电信号，并将其与内部参考压力传感器输出进行比较。 结果的显示优选地在每个步骤计算出的百分比误差。 压力传感器的设置通过为校准仪器提供响应于UUT调整的色调和视觉信号的能力，进行校准，从而提供对被测换能器的零点和量程范围的检测和量的调整。
-
-
-
-
搜索结果
5 条记录 (耗时 0.011 秒)
