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1. 发明授权

US4844858A Reactor cavity dosimetry system and method 失效
标题翻译：反应器腔剂量测定系统及方法
公开(公告)号：US4844858A
公开(公告)日：1989-07-04
申请号：US32861
申请日：1987-03-31
申请人： Arnold H. Fero , Stanwood L. Anderson, Jr. , James Sejvar
发明人： Arnold H. Fero , Stanwood L. Anderson, Jr. , James Sejvar
IPC分类号： G21C17/003
CPC分类号： G21C17/003
摘要： A reactor cavity dosimetry system and method in a nuclear power plant having a reactor vessel and a primary biological shield substantially surrounding the reactor vessel thereby forming a reactor cavity between the vessel and the shield, the system and method providing for remotely and repeatedly positioning a plurality of neutron dosimeters at preselected locations within the cavity, and for withdrawing the dosimeters for analysis thereof and replacing them at the same preselected positions. Assessment of the long-term effects of neutron irradiation on the vessel is enhanced by accurate and repetitive placement of the dosimeters.
摘要翻译：核动力装置中的反应堆腔剂量测定系统和方法，其具有基本上围绕反应器容器的反应器容器和初级生物屏蔽，从而在容器和屏蔽之间形成反应器空腔，所述系统和方法提供远程和重复定位多个的中子剂量计在腔内的预选位置处，并且用于取出用于分析的剂量计并在相同的预选位置替换它们。通过准确和重复放置剂量计，可以增强中子照射对血管的长期影响。

2. 发明申请

US20120257706A1 REACTOR VESSEL INTERNALS RADIATION ANALYSES 审中-公开
标题翻译：反应器船内径辐射分析
公开(公告)号：US20120257706A1
公开(公告)日：2012-10-11
申请号：US13081805
申请日：2011-04-07
申请人： Gianluca Longoni , Arnold H. Fero , Stanwood L. Anderson , Gregory Alan Fischer
发明人： Gianluca Longoni , Arnold H. Fero , Stanwood L. Anderson , Gregory Alan Fischer
IPC分类号： G21C17/108
CPC分类号： G21C17/003 , G21C17/108 , G21D3/001 , Y02E30/40
摘要： The present invention relates to a computational system and method to analyze a radiation field in a light water nuclear reactor. The system and method include a radiation transport module for performing a neutron and gamma transport calculation of a reactor geometry model of the light water nuclear reactor for at least one fuel cycle; a material analysis module for analyzing flux data calculated by the radiation transport module for materials and/or components within the light water nuclear reactor; and a mobile component tracking module for calculating radiation exposure for components within the light water nuclear reactor which have more than one different location during or between the at least one fuel cycle.
摘要翻译：本发明涉及分析轻水核反应堆中的辐射场的计算系统和方法。该系统和方法包括用于对至少一个燃料循环执行轻水核反应堆的反应器几何模型的中子和γ运输计算的辐射传输模块; 用于分析由所述辐射传输模块计算的用于所述轻水核反应堆内的材料和/或组分的通量数据的材料分析模块; 以及移动部件跟踪模块，用于计算轻水核反应堆内部或在至少一个燃料循环之间具有多于一个不同位置的部件的辐射暴露。

3. 发明授权

US4980118A Nuclear power generating station equipment qualification method and apparatus 失效
标题翻译：核发电站设备鉴定方法及装置
公开(公告)号：US4980118A
公开(公告)日：1990-12-25
申请号：US437151
申请日：1989-11-16
申请人： Arnold H. Fero , Lawrence M. Potochnik , Ronald W. Riling , Kenneth F. Semethy
发明人： Arnold H. Fero , Lawrence M. Potochnik , Ronald W. Riling , Kenneth F. Semethy
IPC分类号： G21C17/00
CPC分类号： G21C17/00
摘要： Apparatus for monitoring an object piece of qualified equipment in a nuclear power plant includes first passive means for memicking the effect of radiation received by the object piece, second means for mimicking hte effect of a thermal history of the object piece, and means for mounting the first and second mimic means in close proximity to the object piece in the nuclear power plant. In order to generate and maintain evidence to assure that qualified equipment used in such stations will operate on demand, the first and second mimic means, mounted in close proximity to the object piece, are exposed to the environment of a normally operating power plant and periodically analyzed to determine whether the qualified life of the object piece may be extended.
摘要翻译：用于监测核电站中的合格设备的目标件的装置包括：第一被动装置，用于抑制由物体件接收的辐射的影响，第二装置，用于模拟物体的热历史的效果;以及装置，第一和第二模拟装置靠近核电站中的物体。为了产生和保持证据，以确保在这种站中使用的合格设备将按需运行，安装在物体附近的第一和第二模拟装置暴露于正常工作的发电厂的环境中并且周期性地分析以确定物件的合格寿命是否可以延长。

4. 发明授权

US4881247A Measuring nuclear fuel burnup 失效
标题翻译：测量核燃料燃耗
公开(公告)号：US4881247A
公开(公告)日：1989-11-14
申请号：US325016
申请日：1989-03-16
申请人： Richard C. Smith , John Bartko , Arnold H. Fero
发明人： Richard C. Smith , John Bartko , Arnold H. Fero
IPC分类号： G21C17/06
CPC分类号： G21C17/063
摘要： Disclosed is a method and apparatus for measuring the burnup of nuclear fuel. A curve giving the calculated relationship between the fast neutron emission rate and the burnup of fuel is prepared. The fast neutron counting rate from a sample of nuclear fuel of known burnup is measured and the proportionality ratio between that measurement and the fast neutron emission given by the curve for the same burnup is determined. The fast neutron counting rate of nuclear fuel of unknown burnup is then measured and multiplied by the proportionality ratio to determine the fast neutron emission rate, from which the unknown burnup is then determined by means of the curve.
摘要翻译：公开了一种用于测量核燃料燃耗的方法和装置。给出了快中子排放速率和燃料燃耗之间计算关系的曲线。测量已知燃耗的核燃料样品的快中子计数率，并确定该测量与同一燃耗曲线给出的快中子发射之间的比例比。然后测量未知燃耗的核燃料的快中子计数率并乘以比例比，以确定快中子排放速率，然后通过曲线确定未知燃耗。

5. 发明申请

US20130153715A1 Support Apparatus for Supporting Dosimetry System in Proximity to Reactor Apparatus 有权
标题翻译：用于支持测量系统靠近反应器设备的支持装置
公开(公告)号：US20130153715A1
公开(公告)日：2013-06-20
申请号：US13329497
申请日：2011-12-19
申请人： Joel A. Kulesza , Arnold H. Fero , Alexander W. Harkness
发明人： Joel A. Kulesza , Arnold H. Fero , Alexander W. Harkness
IPC分类号： G21C19/00
CPC分类号： G01T1/02 , G21C13/00 , G21C13/02 , G21C17/10 , G21D1/00 , G21D3/04 , Y02E30/40
摘要： An improved support apparatus is structured to support a dosimetry system within an interior region of a containment apparatus. The dosimetry system is supported in a region between an interior surface of the containment apparatus and an exterior surface of a reactor apparatus that is disposed within the interior of the containment apparatus. The support apparatus includes a retention apparatus having a plurality of brace elements that each have a receptacle formed therein. The receptacles are aligned with one another when installed within the interior of the containment apparatus. The support apparatus further includes a tube apparatus that includes a plurality of tube segments that are connectable together. The dosimetry system is situated within an elongated cavity formed in the tube apparatus. The tube apparatus is situated in the receptacles and thereby supports the dosimetry system on the containment apparatus.
摘要翻译：改进的支撑装置被构造成支撑在容纳装置的内部区域内的剂量测定系统。剂量测定系统被支撑在容纳设备的内表面和设置在容纳设备内部的反应器设备的外表面之间的区域中。支撑装置包括具有多个支撑元件的保持装置，每个支撑元件都具有形成在其中的插座。当安装在容纳设备内部时，容器彼此对准。支撑装置还包括管装置，其包括可连接在一起的多个管段。剂量测定系统位于形成在管装置中的细长空腔内。管装置位于容器中，从而在容纳装置上支撑剂量测定系统。

6. 发明授权

US06252923B1 In-situ self-powered monitoring of stored spent nuclear fuel 有权
标题翻译：储存的乏核燃料的现场自供电监测
公开(公告)号：US06252923B1
公开(公告)日：2001-06-26
申请号：US09371720
申请日：1999-08-10
申请人： John M. Iacovino , Thomas V. Congedo , William A. Byers , Abdul R. Dulloo , Frank H. Ruddy , David F. McLaughlin , Arnold H. Fero , Brandon Damon Thomas , John G. Siedel
发明人： John M. Iacovino , Thomas V. Congedo , William A. Byers , Abdul R. Dulloo , Frank H. Ruddy , David F. McLaughlin , Arnold H. Fero , Brandon Damon Thomas , John G. Siedel
IPC分类号： G21C1706
CPC分类号： G21C17/06 , G21F5/06 , G21Y2002/502 , G21Y2004/304
摘要： Detectors are used to monitor the status of spent nuclear fuel storage containers non-invasively while they remain in storage casks. The detectors measure neutron flux and &ggr;-ray flux and may also measure temperature variations of the spent nuclear fuel. The measurements can be accomplished actively or passively, with minimal exposure of individuals to radiation fields or other hazardous conditions. Preferred neutron and &ggr;-ray detectors have a semiconductor active region that is resistant to neutron damage. Incipient structural failures may also be detected using measurements based on electrical continuity, with data being transmitted to an external pickup coil.
摘要翻译：检测器用于在残留在储存桶中时非侵入性地监测废核燃料储存容器的状态。检测器测量中子通量和γ射线通量，并且还可以测量废核燃料的温度变化。测量可以主动或被动地完成，个人对辐射场或其他危险状况的暴露最少。优选的中子和γ射线检测器具有耐中子损伤的半导体有源区。也可以使用基于电连续性的测量来检测初始结构故障，数据被传送到外部拾取线圈。

7. 发明授权

US5699394A Thermal insulating barrier and neutron shield providing integrated protection for a nuclear reactor vessel 失效
标题翻译：隔热屏障和中子屏蔽为核反应堆提供综合保护
公开(公告)号：US5699394A
公开(公告)日：1997-12-16
申请号：US502236
申请日：1995-07-13
申请人： Roger B. Schreiber , Arnold H. Fero , James Sejvar
发明人： Roger B. Schreiber , Arnold H. Fero , James Sejvar
IPC分类号： G21C11/08 , G21C15/12 , G21C15/18 , G21F3/00
CPC分类号： G21C11/08 , G21C15/18 , G21Y2002/40 , Y02E30/40
摘要： The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel to form a chamber which can be flooded with cooling water through passive valving to directly cool the reactor vessel in the event of a severe accident. The passive valving also includes bistable vents at the upper end of the thermal insulating barrier for releasing steam. A removable, modular neutron shield extending around the upper end of the reactor cavity below the nozzles forms with the upwardly and outwardly tapered transition on the outer surface of the reactor vessel, a labyrinthine channel which reduces neutron streaming while providing a passage for the escape of steam during a severe accident, and for the cooling air which is circulated along the reactor cavity walls outside the thermal insulating barrier during normal operation of the reactor.
摘要翻译：在反应堆空腔中从冷腿喷嘴悬挂的核反应堆装置的反应堆容器设置有与反应器容器隔开的下部隔热屏障，以形成可以通过无源阀充满冷却水直至冷却的室发生严重事故的反应堆船只。被动阀还包括用于释放蒸汽的隔热屏障上端的双稳态通风口。一个可拆卸的模块化中子屏蔽层，围绕喷嘴下方的反应器空腔的上端延伸，形成反应堆容器外表面上的向上和向外的锥形过渡，迷宫式通道，减少中子流动，同时为逃逸提供通道在严重事故期间的蒸汽，以及在反应堆的正常操作期间沿着隔热屏障外部的反应堆空腔壁循环的冷却空气。

8. 发明授权

US4876058A Nuclear power generating station equipment qualification method and apparatus 失效
标题翻译：核发电站设备鉴定方法及装置
公开(公告)号：US4876058A
公开(公告)日：1989-10-24
申请号：US104733
申请日：1987-10-05
申请人： Arnold H. Fero , Lawrence M. Potochnik , Ronald W. Riling , Kenneth F. Semethy
发明人： Arnold H. Fero , Lawrence M. Potochnik , Ronald W. Riling , Kenneth F. Semethy
IPC分类号： G21C17/00 , G21C17/003
CPC分类号： G21C17/00
摘要： Apparatus for monitoring an object piece of qualified equipment in a nuclear power plant includes passive means for detecting a total integrated dose of radiation received by the object piece, means for determining a thermal history of the object piece, and means for housing the passive detection means and determining means in close proximity to the object piece. In order to generate and maintain evidence to assure that qualified equipment used in such stations will operate on demand, the passive detection means and determining means mounted in close proximity to the object piece are exposed to the environment of a normally operating power plant and periodically analyzed to determine whether the qualified life of the object piece may be extended.

9. 发明授权

US08891722B2 Support apparatus for supporting dosimetry system in proximity to reactor apparatus 有权
标题翻译：用于在反应器装置附近支持剂量测定系统的支撑装置
公开(公告)号：US08891722B2
公开(公告)日：2014-11-18
申请号：US13329497
申请日：2011-12-19
申请人： Joel A. Kulesza , Arnold H. Fero , Alexander W. Harkness
发明人： Joel A. Kulesza , Arnold H. Fero , Alexander W. Harkness
IPC分类号： G01T1/02
CPC分类号： G01T1/02 , G21C13/00 , G21C13/02 , G21C17/10 , G21D1/00 , G21D3/04 , Y02E30/40
摘要： An improved support apparatus is structured to support a dosimetry system within an interior region of a containment apparatus. The dosimetry system is supported in a region between an interior surface of the containment apparatus and an exterior surface of a reactor apparatus that is disposed within the interior of the containment apparatus. The support apparatus includes a retention apparatus having a plurality of brace elements that each have a receptacle formed therein. The receptacles are aligned with one another when installed within the interior of the containment apparatus. The support apparatus further includes a tube apparatus that includes a plurality of tube segments that are connectable together. The dosimetry system is situated within an elongated cavity formed in the tube apparatus. The tube apparatus is situated in the receptacles and thereby supports the dosimetry system on the containment apparatus.
摘要翻译：改进的支撑装置被构造成支撑在容纳装置的内部区域内的剂量测定系统。剂量测定系统被支撑在容纳设备的内表面和设置在容纳设备内部的反应器设备的外表面之间的区域中。支撑装置包括具有多个支撑元件的保持装置，每个支撑元件都具有形成在其中的插座。当安装在容纳设备内部时，容器彼此对准。支撑装置还包括管装置，其包括可连接在一起的多个管段。剂量测定系统位于形成在管装置中的细长空腔内。管装置位于容器中，从而在容纳装置上支撑剂量测定系统。

10. 发明授权

US5781602A PGNAA system for non-invasively inspecting RPV weld metal in situ, to determine the presence and amount of trace embrittlement-enhancing element 失效
标题翻译： PGNAA系统，用于非原位检测RPV焊接金属，以确定痕量脆化增强元素的存在和数量
公开(公告)号：US5781602A
公开(公告)日：1998-07-14
申请号：US649370
申请日：1996-05-17
申请人： Arnold H. Fero , Stanwood L. Anderson , Thomas V. Congedo , Abdul R. Dulloo , Francis H. Ruddy
发明人： Arnold H. Fero , Stanwood L. Anderson , Thomas V. Congedo , Abdul R. Dulloo , Francis H. Ruddy
IPC分类号： B23K31/12 , G01N23/222 , G21C17/003
CPC分类号： G01N23/222 , B23K31/12 , G21C17/003 , G21Y2002/204
摘要： Prompt Gamma Neuteon Activation Analysis (PGNAA) is employed to determined in situ the content of nickel, copper, or other embrittlement-enhancing elements within the weld metal joints of nuclear reactor pressure vessels.
摘要翻译：采用快速伽马激发分析法（PGNAA）来原位测定核反应堆压力容器焊缝金属接头内镍，铜或其他脆化增强元素的含量。

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