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1. 发明授权

US4877575A Core reactivity validation computer and method 失效
标题翻译：核心反应性验证计算机和方法
公开(公告)号：US4877575A
公开(公告)日：1989-10-31
申请号：US145177
申请日：1988-01-19
申请人： Albert J. Impink, Jr. , Francis L. Langford, Jr. , Louis R. Grobmyer , William K. Luinetti
发明人： Albert J. Impink, Jr. , Francis L. Langford, Jr. , Louis R. Grobmyer , William K. Luinetti
IPC分类号： G21C17/00 , G21C7/36 , G21C17/108 , G21D3/10
CPC分类号： G21D3/10 , G21C7/36 , Y02E30/39
摘要： A smart reactivity computer is disclosed that processes signals from multiple neutron detectors to generate values of regional core reactivity that are output to a strip chart recorder. The computer compares the regional reactivity values and, when the values are coincident for a period sufficient to satisfy a statistical fit test to a straight line, indicates to the operator that true core reactivity can be determined. The computer determines control rod worth by first fitting a straight line to the coincident portion of the reactivity values. The computer then determines intersections between the straight line and the reactivity value lines produced when the control rods are moved on both ends of the straight line. The difference between intersections for a single control rod movement line determines control rod worth for that movement.

2. 发明授权

US4588547A Method and apparatus for determining the nearness to criticality of a nuclear reactor 失效
标题翻译：确定核反应堆临界性接近度的方法和装置
公开(公告)号：US4588547A
公开(公告)日：1986-05-13
申请号：US540073
申请日：1983-10-07
申请人： Albert J. Impink, Jr. , Francis L. Langford, Jr.
发明人： Albert J. Impink, Jr. , Francis L. Langford, Jr.
IPC分类号： G21C17/00 , G21C17/10 , G21C17/104
CPC分类号： G21C17/104
摘要： The approach to criticality of a nuclear reactor provided with an artificial neutron source is monitored by two neutron detectors, one which measures the neutron flux in a localized region around the artificial neutron source, and the other located simlarly with respect to the core geometry but removed from the localized region. When the reactor is subcritical, the artificial source dominates and the outputs of the two detectors are noticeably different. As the reactor approaches criticality, the critical mode distribution of neutrons, which is symmetrical with respect to the two detectors, becomes dominant and the detector outputs approach each other in magnitude. The ratio of the output signals therefore, provides an indication of the reactor reactivity state. Either linear or logarithmic ratio signals can be generated, and if desired, either can be compared with an appropriately scaled reference signal representative of a selected reactivity state, such as a multiplication factor of 0.99, with the result of the comparison used to control a "near-criticality/not near-criticality" logic output.
摘要翻译：提供有人造中子源的核反应堆的关键性的方法由两个中子探测器监测，该探测器测量人造中子源周围的局部区域中的中子通量，另一个位于与核心几何形状相似的位置从本地化地区。当反应堆为亚临界时，人造源占主导地位，两个检测器的输出明显不同。随着电抗器接近临界，相对于两个检测器对称的中子的临界模式分布变得占主导地位，并且检测器输出的幅度相互接近。因此，输出信号的比率提供反应堆反应性状态的指示。可以产生线性或对数比率信号，并且如果需要，可以将其与适当缩放的参考信号进行比较，该参考信号表示所选择的反应性状态，例如0.99的倍增因子，其比较结果用于控制“ 近临界/不接近临界“的逻辑输出。

3. 发明授权

US5024801A Reactor core model update system 失效
标题翻译：反应堆核心模型更新系统
公开(公告)号：US5024801A
公开(公告)日：1991-06-18
申请号：US345872
申请日：1989-05-01
申请人： Albert J. Impink, Jr. , Louis R. Grobmyer , Robert E. Sariscak , Toshio Morita , John L. Duryea
发明人： Albert J. Impink, Jr. , Louis R. Grobmyer , Robert E. Sariscak , Toshio Morita , John L. Duryea
IPC分类号： G21C17/00 , G21D3/00
CPC分类号： G21D3/001 , G21C17/00 , Y02E30/39
摘要： The present invention is a system that updates a pressurized water reactor core model, or data file describing the core, periodically using measured values determinable from core instrumentation. The system starts with a calibrated model calibrated from a flux map and a boron concentration measurement both determined monthly. Reactor system measurements are performed and the model is updated from the measurements using a standard depletion calculation. Some of the measured values are also used to determine measured actual values of axial offset and pinch. Standard neutronics equations are used to calculate analytical values of axial offset and pinch from the model, and the measured and calculated values are compared. If a deviation beyond a certain magnitude is detected, buckling coefficients in the model are adjusted to compensate for model drift. The updated model is stored and a time-out period is entered until it is time for another drift compensation cycle to start. The adjustment overcompensates the coefficients until the difference between the measured values and calculated values is slightly less in magnitude than the deviation but of an opposite sign. The adjusted and updated model can be used for accurate initial values of a core predictor or for display to the operator.

4. 发明授权

US5251242A Bi-metallic, self powered, fixed incore detector, and method of calibrating same 失效
标题翻译：双金属，自供电，固定式检测器及其校准方法
公开(公告)号：US5251242A
公开(公告)日：1993-10-05
申请号：US902141
申请日：1992-06-22
申请人： Albert J. Impink, Jr. , Louis R. Grobmyer , Kenneth G. Lunz , Stephen N. Tower
发明人： Albert J. Impink, Jr. , Louis R. Grobmyer , Kenneth G. Lunz , Stephen N. Tower
IPC分类号： G01T3/00 , G21C17/108 , G21C17/00
CPC分类号： G01T3/006 , G21C17/108
摘要： The present invention is a detector assembly for a nuclear reactor which includes platinum detector segments (30-40) axially distributed end to end within a reactor assembly and vanadium detector segments (42-52) spatially congruent in the same assembly. The vanadium detectors calibrate the platinum detector signals to remove the flux contributions of fission products. A full length vanadium detector (62) and a full length platinum detector (90) can be substituted and used to determine the compensation for the platinum detector segments (30-40). The compensated platinum detector signals, wherein compensation consists of isolating that portion of the total platinum detector signal that is directly proportional to the current local heat deposition rate in the reactor fuel, can be used for reactor core protection purposes.
摘要翻译：本发明是用于核反应堆的检测器组件，其包括在反应器组件内端对端轴向分布的铂检测器段（30-40）和在同一组件中空间上一致的钒检测器段（42-52）。钒检测器校准铂检测器信号以去除裂变产物的助熔剂。可以取代全长钒检测器（62）和全长铂检测器（90），以确定铂检测器段（30-40）的补偿。补偿的铂检测器信号，其中补偿包括隔离与反应堆燃料中的当前局部热沉积速率成正比的总铂检测器信号的一部分，可用于反应堆堆芯保护目的。

5. 发明授权

US4839134A Continuous, online nuclear power distribution synthesis system and method 失效
标题翻译：连续在线核电配电合成系统及方法
公开(公告)号：US4839134A
公开(公告)日：1989-06-13
申请号：US140065
申请日：1987-12-31
申请人： Albert J. Impink, Jr. , Louis R. Grobmyer
发明人： Albert J. Impink, Jr. , Louis R. Grobmyer
IPC分类号： G21C17/00 , G21C17/10
CPC分类号： G21C17/10
摘要： The present invention provides a power distribution synthesis system that uses a small number of local axial power distributions determined from less than a full complement of fixed incore neutron detectors and a power sharing map produced from a full complement of core exit thermocouple temperature signals to synthesize the full core power distribution. The localized tilt of the core is determined from the power sharing map and used to remove the tilt from the local distribution. The tilt adjusted local distribution is assigned to symmetric core locations where uninstrumented core power values are determined by interpolation. The interpolated, assigned and tilt corrected local distribution power values are transformed into the three dimensional power distribution using the tilt.

6. 发明授权

US5229066A Control rod position indication system 失效
标题翻译：控制杆位置指示系统
公开(公告)号：US5229066A
公开(公告)日：1993-07-20
申请号：US740354
申请日：1991-08-05
申请人： Albert J. Impink, Jr. , Michael D. Heibel , Louis R. Grobmyer
发明人： Albert J. Impink, Jr. , Michael D. Heibel , Louis R. Grobmyer
IPC分类号： G21C17/10 , G21C7/12 , G21C7/36
CPC分类号： G21C7/12 , G21C7/36 , G21Y2002/204 , G21Y2004/401 , Y02E30/39
摘要： The present invention is a system which determines nuclear reactor control rod axial position using a deviation signature database generated from a current or reference signal pattern produced by one or more strings of axially dispersed fixed incore detector sections in the reactor core. The deviation signature database is produced by assuming deviant axial positions for the control rods in the core, calculating expected detector signals for the assumed positions and storing the deviation of expected signals from a calibration reference along with corresponding assumed rod positions. The signature database is periodically updated to take into account changed core conditions. When a change in detector responses is detected the system performs a signature analysis of the deviations in the signature database using the current deviation from the reference to search for the closest match. The change indicates not only the bank or individual rod that has moved but also the direction of movement allowing the search of the database to be circumscribed to the portion associated with the bank or individual rod and direction of movement. The closest match is used to incrementally search for the exact rod position by calculating expected response deviations for each assumed incremental move and comparing the expected response deviation to actual response deviations. If the system searches past the actual position, the last assumed position is output.
摘要翻译：本发明是一种使用由反应堆堆芯中的一个或多个轴向分散的固定不动检测器部分串产生的当前或参考信号图形产生的偏差特征数据库来确定核反应堆控制棒轴向位置的系统。通过假设核心中的控制棒的偏离的轴向位置来计算偏差特征数据库，计算假设位置的预期检测器信号，并且存储来自校准基准的预期信号的偏差以及相应的假定的杆位置。定期更新签名数据库以考虑更改的核心条件。当检测器响应的变化被检测到时，系统使用当前偏离参考来搜索最接近的匹配来对签名数据库中的偏差进行签名分析。该变化不仅指示已经移动的堤或单个杆，而且还指示移动方向，允许将数据库的搜索限制到与堤或单独杆和移动方向相关联的部分。最接近的匹配用于通过计算每个假设的增量移动的预期响应偏差并将预期响应偏差与实际响应偏差进行比较来逐步搜索精确的杆位置。如果系统搜索超过实际位置，则输出最后的假定位置。

7. 发明授权

US4927594A Thermocouple based control rod position indication system 失效
标题翻译：基于热电偶的控制杆位置指示系统
公开(公告)号：US4927594A
公开(公告)日：1990-05-22
申请号：US230393
申请日：1988-08-10
申请人： Michael D. Heibel , Albert J. Impink, Jr. , Louis R. Grobmyer
发明人： Michael D. Heibel , Albert J. Impink, Jr. , Louis R. Grobmyer
IPC分类号： G21C17/10 , G21C17/12 , G21D3/10
CPC分类号： G21C17/12 , G21D3/10 , Y02E30/40
摘要： The present invention obtains enthalpy rise deviations in core power distribution using core exit thermocouples 18 and an inlet temperature detector 20. The enthalpy rise deviations are used to determine control rod position change relative a rod reference position. Because rod position change is linear with respect to enthalpy deviation, the change can be determined from the slope using the deviation. By adding the change to a reference rod position the actual rod position can be determined.

8. 发明授权

US4774049A Two and three dimensional core power distribution monitor and display 失效
标题翻译：二维和三维核心配电监控和显示
公开(公告)号：US4774049A
公开(公告)日：1988-09-27
申请号：US850196
申请日：1986-04-10
申请人： Albert J. Impink, Jr. , Louis R. Grobmyer
发明人： Albert J. Impink, Jr. , Louis R. Grobmyer
IPC分类号： G21C17/00 , G21C17/02 , G21C17/10
CPC分类号： G21C17/10
摘要： A method and apparatus for monitoring and generating on-line, real time displays of two and three dimensional nuclear reactor core power distributions and off-line, periodically updated summaries of three dimensional nuclear reactor core power and burnup distributions is disclosed. The method and apparatus makes use of information obtained from inlet sensors and core-exit thermocouples to produce enthalpy rise values. Flux measurements are combined with enthalpy to produce power values. In one aspect of the invention, deviations from reference values are classified and displayed on a two-dimensional color graphics terminal where the various classifications are displayed according to a color code which enables a rapid and convenient method of analysis of the dynamics of the reactor operation.
摘要翻译：公开了一种用于监测和生成二维和三维核反应堆核心功率分布的在线实时显示的方法和装置，并且公开了三维核反应堆核心功率和燃耗分布的离线，定期更新的概述。该方法和装置利用从入口传感器和芯出口热电偶获得的信息产生焓值上升值。通量测量与焓组合以产生功率值。在本发明的一个方面中，与参考值的偏差被分类并显示在二维彩色图形终端上，其中根据能够快速方便地分析反应堆操作的动力学的颜色代码来显示各种分类。

9. 发明授权

US5089978A Automatic plant state diagnosis system including a display selection system for selecting displays responsive to the diagnosis 失效
标题翻译：自动植物状态诊断系统，包括用于选择对诊断显示的显示选择系统
公开(公告)号：US5089978A
公开(公告)日：1992-02-18
申请号：US479007
申请日：1990-02-09
申请人： Melvin H. Lipner , Albert J. Impink, Jr.
发明人： Melvin H. Lipner , Albert J. Impink, Jr.
IPC分类号： G01D21/00 , G05B23/02 , G06F1/00 , G06F11/22 , G06F11/32 , G21C17/00 , G21D3/04
CPC分类号： G21D3/001 , G05B23/0267 , G21C17/00 , G21D3/04 , Y02E30/40
摘要： The present invention is a system that diagnoses plant state in conditions where plant state cannot be precisely determined from sensor signals. If a state is diagnosed with certainty an appropriate plant procedure step display is provided to the operator. If not, the steps corresponding to the likely states are displayed to the operator ranked according to the likelihood of being in that state. The operator can select a step or a time out will result in the highest likelihood step being selected. An appropriate step display is then provided to the operator. The system can also indicate to the operator the consequences of allowing that plant state to continue as well as provide recommendations concerning the currently diagnosed state.

10. 发明授权

US4801421A On-line monitoring and analysis of reactor vessel integrity 失效
标题翻译：在线监测和分析反应堆容器的完整性
公开(公告)号：US4801421A
公开(公告)日：1989-01-31
申请号：US26501
申请日：1987-03-16
申请人： D. Scott Ackerson , Albert J. Impink, Jr. , Kenneth R. Balkey , Timothy S. Andreychek
发明人： D. Scott Ackerson , Albert J. Impink, Jr. , Kenneth R. Balkey , Timothy S. Andreychek
IPC分类号： G21C17/003 , G21C13/08 , G21C17/00 , G21C17/108
CPC分类号： G21C13/08 , G21C17/00 , G21C17/108 , Y02E30/40
摘要： A real time analysis of nuclear reactor vessel integrity is preformed by monitoring reactor coolant temperature and pressure and fast neutron fluence, and generating therefrom a visual comparison of the reference nil-ductility transition temperature, RT.sub.ndt, required for flaw initiation and the actual RT.sub.ndt through the entire depth of the vessel wall at selected critical locations. When flaw initiation is indicated at any depth, the RT.sub.ndt required for flaw propagation arrest is also generated and displayed. A display can also be generated to provide guidance for optimum performance during heatup and cooldown. Thermocouples located at the reactor core inlet are used in conjunction with the resistance temperature detectors, RTDs, conventionally provided in the cold leg conduits to generate a more accurate measurement of the coolant temperature at the critical locations in the vessel. Under stagnant flow conditions a correlation is applied to the RTD readings to provide the best estimate of coolant temperature at the critical locations.
摘要翻译：核反应堆容器完整性的实时分析是通过监测反应堆冷却剂温度和压力以及快中子通量来实现的，并通过对其产生缺陷引发所需的参考无延展转变温度RTndt和通过实际RTndt进行视觉比较在选定的关键位置的血管壁的整个深度。当在任何深度指示缺陷开始时，也产生并显示缺陷传播停止所需的RTndt。还可以生成显示器，以提供在加热和冷却期间的最佳性能的指导。位于反应堆核心入口处的热电偶与冷腿管道中通常设置的电阻温度检测器RTD结合使用，以在容器中的关键位置产生更准确的冷却剂温度测量。在停滞的流动条件下，将相关性应用于RTD读数，以提供关键位置的冷却剂温度的最佳估计。

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