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1. 发明授权

US5076862A Method of manufacturing heat resisting magnetic scale 失效
标题翻译：制造耐热磁性尺度的方法
公开(公告)号：US5076862A
公开(公告)日：1991-12-31
申请号：US513967
申请日：1990-04-24
申请人： Katsuyuki Ara , Hideyuki Yagi , Hideo Ikeda , Toshitsugu Ohmura , Megumi Ohmine , Masaharu Moriyasu
发明人： Katsuyuki Ara , Hideyuki Yagi , Hideo Ikeda , Toshitsugu Ohmura , Megumi Ohmine , Masaharu Moriyasu
IPC分类号： G01V15/00 , H01F1/00
CPC分类号： G01V15/00 , Y10S148/903 , Y10T428/12465
摘要： A method of manufacturing a heat resisting magnetic scale is disclosed which comprises a manufacturing process in which at least a part of a heat resisting base is heated and immediately cooled for the purpose of fusing the heated part to the base and changing both the magnetic characteristics of the part of the base which has been heated and the Curie point of the part which has been heated is raised to 100.degree. C. or higher.
摘要翻译：公开了一种制造耐热磁性标尺的方法，该方法包括一个制造工艺，其中加热耐热基体的至少一部分并立即冷却，以便将被加热部分熔合到基底上并改变两者的磁特性被加热的基部的一部分和被加热部分的居里点升高到100℃以上。

2. 发明授权

US4935070A Method of manufacturing heat resisting magnetic scale 失效
标题翻译：制造耐热磁铁的方法
公开(公告)号：US4935070A
公开(公告)日：1990-06-19
申请号：US237384
申请日：1988-08-29
申请人： Katsuyuki Ara , Hideyuki Yagi , Hideo Imeda , Toshitsugu Ohmura , Megumi Ohmine , Masaharu Moriyasu
发明人： Katsuyuki Ara , Hideyuki Yagi , Hideo Imeda , Toshitsugu Ohmura , Megumi Ohmine , Masaharu Moriyasu
IPC分类号： G01V15/00
CPC分类号： G01V15/00 , Y10S148/903
摘要： A method of manufacturing a heat resisting magnetic scale is disclosed which comprises a manufacturing process in which at least a part of a heat resisting base is heated and a manufacturing process in which the part which has been heated is immediately cooled down for the purpose of changing the magnetic characteristics of the part of the base which has been heated and the Curie point of the part which has been heated is raised to 100.degree. C. or higher.A heating resisting magnetic scale which cannot be demagnetized at high temperatures and cannot be separated even if it is subjected to rapid change in temperatures, and which exhibits excellent stability and measuring precision.
摘要翻译：公开了一种制造耐热磁性标尺的方法，该方法包括加热至少一部分耐热基底的制造过程，并且已经加热的部件被立即冷却以便改变的制造过程被加热的基底部分的磁特性和加热部分的居里点升高到100℃以上。耐高温磁性标尺，即使经受快速变化，也不能在高温下退磁，不能分离，稳定性和测量精度优异。

3. 发明授权

US5544207A Apparatus for measuring the thickness of the overlay clad in a pressure vessel of a nuclear reactor 失效
标题翻译：用于测量包覆在核反应堆的压力容器中的覆层的厚度的装置
公开(公告)号：US5544207A
公开(公告)日：1996-08-06
申请号：US319630
申请日：1994-10-07
申请人： Katsuyuki Ara , Nobuya Nakajima , Noriya Ebine
发明人： Katsuyuki Ara , Nobuya Nakajima , Noriya Ebine
IPC分类号： G01B7/06 , G01B7/00 , G01N27/82 , G21C17/003 , G21C17/01
CPC分类号： G21C17/01 , G01B7/105 , G21Y2002/204 , G21Y2004/30 , G21Y2004/40
摘要： A method of and an apparatus for measuring the thickness of the overlay clad of the pressure vessel of a nuclear reactor with good accuracy are disclosed. A magnetic yoke having an appropriate length and cross-sectional area of the magnetic path is placed closely in contact with the surface of the overlay clad of the pressure vessel of the nuclear reactor to form a magnetic path by the magnetic yoke and the pressure vessel of the nuclear reactor, the magnetic yoke is magnetized, the distribution of the magnetic field on or near the surface of the overlay clad in contact with which the magnetic yoke is closely placed is measured and the thickness of the overlay clad of the pressure vessel of the nuclear reactor is identified from the medium value or the half value width of the distribution of the magnetic field thus measured.
摘要翻译：公开了一种用于以高精度测量核反应堆的压力容器的覆盖层的厚度的方法和装置。具有适当的磁路长度和横截面面积的磁轭被放置成与核反应堆的压力容器的覆盖层的表面紧密接触，以便通过磁轭和压力容器核反应堆，磁轭被磁化，测量了磁轭靠近的覆盖层接触的表面上或附近的磁场分布，并且测量了磁轭的压力容器的覆盖层的厚度核反应堆是根据所测量的磁场分布的中值或半值宽度来确定的。

4. 发明授权

US4423629A Method and apparatus for sensing liquid level 失效
标题翻译：检测液位的方法和装置
公开(公告)号：US4423629A
公开(公告)日：1984-01-03
申请号：US308903
申请日：1981-10-05
申请人： Katsuyuki Ara , Naoaki Wakayama , Kazuo Kobayashi , Toshihiko Ogasawara
发明人： Katsuyuki Ara , Naoaki Wakayama , Kazuo Kobayashi , Toshihiko Ogasawara
IPC分类号： G01F23/22 , G01F23/24
CPC分类号： G01F23/248
摘要： Method and apparatus for sensing liquid level of the invention includes a plurality of thermocouple elements that are formed by connecting two kind of thermocouple wires alternately in series into a plurality of thermometric contacts. The two kind of thermocouple wires have different thermoelectric powers SA and SB and have a variety of predetermined lengths. The invention can sense with high reliability a liquid level of a sensed liquid by changing electromotive forces from these thermocouple elements into binary signals by using fewer thermocouple elements than the conventional apparatus. The invention also includes thermocouple elements for parity check to self-diagnose the sensed result to inspect easily and securely errors in operation due to disconnections in the thermocouple elements or external noises.
摘要翻译：本发明的检测液面的方法和装置包括通过将两种热电偶线串联连接成多个温度接触形成的多个热电偶元件。两种热电偶线具有不同的热电功率SA和SB，并且具有各种预定长度。通过使用比常规装置更少的热电偶元件，本发明可以通过将这些热电偶元件的电动势改变为二进制信号，以高可靠性感测感测液体的液位。本发明还包括用于奇偶校验的热电偶元件以自我诊断感测结果，以便由于热电偶元件或外部噪声中的断开而容易且安全地检查操作错误。

5. 发明授权

US5687204A Method of and apparatus for checking the degradation of a pressure vessel of a nuclear reactor 失效
标题翻译：用于检查核反应堆压力容器退化的方法和装置
公开(公告)号：US5687204A
公开(公告)日：1997-11-11
申请号：US319629
申请日：1994-10-07
申请人： Katsuyuki Ara , Nobuya Nakajima , Noriya Ebine
发明人： Katsuyuki Ara , Nobuya Nakajima , Noriya Ebine
IPC分类号： G21C13/087 , G21C17/003 , G21C17/00
CPC分类号： G21C13/087 , G21C17/003 , G21Y2002/102 , G21Y2002/204 , Y02E30/40
摘要： In a method of and an apparatus for checking the degradation of the pressure vessel of a nuclear reactor with the pressure vessel of the nuclear reactor being directly measured in a non-destructive manner, a magnetic yoke having an exciting coil and a magnetic flux measuring coil is closely placed in contact with the inner wall of the pressure vessel of the nuclear reactor. The hysteresis magnetization characteristics of the closed magnetic path formed by the magnetic yoke and the pressure vessel of the nuclear reactor are measured. The coercive forces are obtained by the hysteresis characteristics. The hardness of the material comprising the pressure vessel of the nuclear reactor at the part of the magnetic path formed in the pressure vessel of the nuclear reactor is obtained from the coercive forces and the degradation of the material comprising the pressure vessel is checked from the hardness.
摘要翻译：在以非破坏性方式直接测量核反应堆的压力容器的核反应堆的压力容器的劣化检测方法和装置中，具有励磁线圈和磁通量测量线圈的磁轭紧密地与核反应堆的压力容器的内壁接触。测量由磁轭和核反应堆的压力容器形成的闭合磁路的磁滞特性。矫顽力通过滞后特性得到。由核反应堆的压力容器中形成的磁路部分的核反应堆的压力容器的材料的硬度是由矫顽力获得的，并且从包含压力容器的材料的劣化可以从硬度。

6. 发明授权

US5323430A Method and system for fine control of thermal power of a boiling water reactor with natural circulation 失效
标题翻译：具有自然循环的沸水反应堆热功率的精细控制方法和系统
公开(公告)号：US5323430A
公开(公告)日：1994-06-21
申请号：US2697
申请日：1993-01-11
申请人： Pieter K. Termaat , Katsuyuki Ara
发明人： Pieter K. Termaat , Katsuyuki Ara
IPC分类号： G21C17/035 , G21C17/00
CPC分类号： G21C17/035 , G21Y2002/204 , G21Y2004/40
摘要： A method and a system for fine control of the thermal power of a nuclear boiling water reactor (BWR) with natural circulation. The reactor vessel, in which the core of such a reactor is enclosed, embodies an in-vessel part of a water level gauge containing a water level sensor, such that together with the out-of-vessel part of the system, which is a signal conditioning and processing unit, the effective water level in the vessel can accurately be measured and adjusted either automatically or by hand. The in-vessel part of the system comprises a water level gauge, such as a vertical standpipe, in which the "steam-collapsed" or "effective" water level is accurately created. The effective water level is typically defined for a reactor vessel of a normally operating boiling water reactor (BWR), while partly containing liquid water, partly a mixture of steam and water, and partly just steam. A ternary-coding, hybrid digital/analog thermocouple sensor with stand-alone capability is enclosed in the water level gauge, providing ternary-coded (-1, 0, +1) as well as analog (amplitude) signaling, such that by using an appropriate signal conditioning and processing unit, the water level in the gauge, relative to a reference level, is uniquely and very accurately determined. By the beneficial use of the analog information on water level contained in the signal transition curves, in addition to the digital information of the sensor signals, continuous water level readings can be obtained over the whole of a designed water level measuring range, this being independent of reactor water temperature or pressure. This accurate continuous level-measuring system is not limited to use in boiling water reactors, nor to water as a level-forming liquid.
摘要翻译：具有自然循环的核沸水反应堆（BWR）的热力精细控制的方法和系统。将这种反应器的核心封闭在其中的反应堆容器包含含有水位传感器的水位计的容器内部分，使得与系统的不合格部分一起，其为信号调理和处理单元，可以精确地自动或手动测量和调整容器内的有效水位。系统的容器部分包括诸如垂直立管的水位计，其中精确地产生“蒸汽塌陷”或“有效”水位。通常为正常操作的沸水反应堆（BWR）的反应堆容器定义有效水位，而部分地包含液态水，部分是蒸汽和水的混合物，以及部分仅仅是蒸汽。具有独立功能的三进制编码，混合数字/模拟热电偶传感器封装在水位计中，提供三进制编码（-1,0，+1）以及模拟（振幅）信号，使得通过使用适当的信号调理和处理单元，量规中的水位相对于参考水平是唯一且非常准确地确定的。通过对信号转换曲线中包含的水位的模拟信息的有益使用，除了传感器信号的数字信息之外，可以在整个设计的水位测量范围内获得连续的水位读数，这是独立的的反应堆水温或压力。这种精确的连续液位测量系统不限于在沸水反应器中使用，也不限于用作水平形成液体的水。

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