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1.发明授权Monte Carlo criticality-mode systems and methods for computing neutron and gamma fluence in a nuclear reactor 有权用于计算核反应堆中子和伽马能量密度的蒙特卡洛关键模式系统和方法公开(公告)号：US07233888B2
公开(公告)日：2007-06-19
申请号：US10191620
申请日：2002-07-09
摘要： A method for simulating three-dimensional spatial distribution of neutron and gamma fluences in a nuclear reactor includes, in an exemplary embodiment, generating a detailed geometric configuration of a nuclear reactor core and surrounding components, generating detailed fuel composition and concentration distribution, and calculating three-dimensional nuclide concentrations for the fuel rods and the water surrounding the fuel rods using the generated geometric configuration and generation fuel composition and concentration distributions. The method also includes calculating neutron and gamma fluxes using a Monte Carlo radiation transport criticality mode methodology, and generating a neutron and gamma fluence map for predetermined areas of the reactor.
摘要翻译： 用于模拟核反应堆中的中子和伽马能量的三维空间分布的方法包括在示例性实施例中产生核反应堆核心和周围部件的详细几何构型，产生详细的燃料组成和浓度分布，以及计算三 使用生成的几何构型和产生燃料组成和浓度分布，燃料棒和燃料棒周围的水的三维核素浓度。 该方法还包括使用蒙特卡罗辐射传输临界模式方法计算中子和伽马通量，以及产生用于反应堆的预定区域的中子和γ注量图。
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2.发明申请DETECTING PIN DIVERSION FROM PRESSURIZED WATER REACTORS SPENT FUEL ASSEMBLIES 有权从加压水反应堆检测发动机燃料组件的引脚分流公开(公告)号：US20110026661A1
公开(公告)日：2011-02-03
申请号：US12619791
申请日：2009-11-17
申请人： Young S. Ham , Shivakumar Sitaraman
发明人： Young S. Ham , Shivakumar Sitaraman
CPC分类号： G21C17/06
摘要： Detecting diversion of spent fuel from Pressurized Water Reactors (PWR) by determining possible diversion including the steps of providing a detector cluster containing gamma ray and neutron detectors, inserting the detector cluster containing the gamma ray and neutron detectors into the spent fuel assembly through the guide tube holes in the spent fuel assembly, measuring gamma ray and neutron radiation responses of the gamma ray and neutron detectors in the guide tube holes, processing the gamma ray and neutron radiation responses at the guide tube locations by normalizing them to the maximum value among each set of responses and taking the ratio of the gamma ray and neutron responses at the guide tube locations and normalizing the ratios to the maximum value among them and producing three signatures, gamma, neutron, and gamma-neutron ratio, based on these normalized values, and producing an output that consists of these signatures that can indicate possible diversion of the pins from the spent fuel assembly.
摘要翻译： 通过确定可能的转移来检测来自加压水反应堆（PWR）的乏燃料转移，包括提供包含伽马射线和中子探测器的探测器组的步骤，将包含伽马射线和中子探测器的探测器组通过导轨插入乏燃料组件 废燃料组件中的管孔，测量导管孔中伽马射线和中子检测器的伽马射线和中子辐射响应，通过将导管管位置处的伽马射线和中子辐射响应归一化为最大值 一组响应，并将导管位置处的伽马射线和中子响应的比例归一化，并将比率归一化为最大值，并根据这些归一化值产生三个特征，γ，中子和γ中子比， 并产生由这些签名组成的输出，这些签名可以指示引脚的可能转移 在乏燃料组件上。
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3.发明申请Systems and methods for estimating helium production in shrouds of nuclear reactors 审中-公开用于估计核反应堆护罩中氦生产的系统和方法公开(公告)号：US20050105675A1
公开(公告)日：2005-05-19
申请号：US10714417
申请日：2003-11-14
IPC分类号： G21C17/003 , G01N33/20 , G21C20060101 , G21C1/08 , G21C17/00 , G21C17/01 , G21C19/00 , G21D1/00
CPC分类号： G21C17/00 , G21C17/003 , G21C17/01 , G21D3/001 , Y02E30/40
摘要： A method for estimating a helium content of the stainless steel core shroud in a boiling water nuclear reactor includes, in an exemplary embodiment, determining a neutron fluence for predetermined areas of the reactor, and estimating a helium content of the stainless steel shroud at predetermined areas of the reactor using the following equation: CHe=1031*(1−e−bj*φj), where CHe is the helium concentration as atomic parts per billion of helium in the stainless steel shroud per weight parts per million of boron in the stainless steel shroud, bj is a value between about 2.50 e−21 and about 5.00 e−21, φj is fluence expressed as neutrons per square centimeter, and subscript j denotes thermal fluence or fast fluence.
摘要翻译： 在示例性实施例中，用于估计沸水核反应堆中的不锈钢芯护罩的氦含量的方法包括确定反应堆的预定区域的中子注量，以及在预定区域估计不锈钢护罩的氦含量 的反应器使用以下等式：C 1 H 2 = 1031 *（1-e）B 1 / 其中C氦是氦浓度，作为不锈钢罩中十亿氦原子的原子数量 在不锈钢护罩中每百万分之一硼的重量百分比是约2.50埃-21至约5.00埃-21 / >，phi 是以中子每平方厘米表示的能量密度，下标j表示热能通量或快速注量。
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公开(公告)号：US4947040A
公开(公告)日：1990-08-07
申请号：US455807
申请日：1989-12-20
IPC分类号： G01V5/10
摘要： A borehole logging method for determining the porosity of a formation surrounding the borehole, comprising the steps of: irradiating the formation surrounding the borehole from a location within the borehole with a burst of neutrons, detecting at a near detector indications of the concentration of thermal neutrons following the burst of neutrons and generating near count rate signals as a function of time in response thereto, detecting at a far detector indications of the concentration of thermal neutrons following the burst of neutrons and generating far count rate signals as a function of time in response thereto, fitting a count rate model to the near count rate signals to determine a near impulse formation count rate amplitude, fitting a count rate model to said far count rate signals to determine a far impulse formation count rate amplitude, determining the ratio of the near and far count rate signals as a characteristic proportional to the porosity of the formation.
摘要翻译： 一种用于确定围绕钻孔的地层的孔隙度的钻孔测井方法，包括以下步骤：用钻井中子从井眼内的位置照射钻孔周围的地层，在近处检测到热中子浓度的指示 在中子脉冲之后并产生近似计数速率信号作为响应于时间的函数，在远检测器处检测指示中子脉冲之后的热中子的浓度，并产生作为响应时间的函数的远计数率信号 将计数速率模型拟合到近计数率信号以确定近似脉冲形成计数速率幅度，将计数速率模型拟合到所述远计数速率信号以确定远冲激形成计数速率幅度，确定近似 和远计数率信号作为与地层孔隙度成比例的特征。
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5.发明授权公开(公告)号：US09543046B2
公开(公告)日：2017-01-10
申请号：US12619791
申请日：2009-11-17
申请人： Young S. Ham , Shivakumar Sitaraman
发明人： Young S. Ham , Shivakumar Sitaraman
IPC分类号： G21C17/06
CPC分类号： G21C17/06
摘要： Detecting diversion of spent fuel from Pressurized Water Reactors (PWR) by determining possible diversion including the steps of providing a detector cluster containing gamma ray and neutron detectors, inserting the detector cluster containing the gamma ray and neutron detectors into the spent fuel assembly through the guide tube holes in the spent fuel assembly, measuring gamma ray and neutron radiation responses of the gamma ray and neutron detectors in the guide tube holes, processing the gamma ray and neutron radiation responses at the guide tube locations by normalizing them to the maximum value among each set of responses and taking the ratio of the gamma ray and neutron responses at the guide tube locations and normalizing the ratios to the maximum value among them and producing three signatures, gamma, neutron, and gamma-neutron ratio, based on these normalized values, and producing an output that consists of these signatures that can indicate possible diversion of the pins from the spent fuel assembly.
摘要翻译： 通过确定可能的转移来检测来自加压水反应堆（PWR）的乏燃料转移，包括提供包含伽马射线和中子探测器的探测器组的步骤，将包含伽马射线和中子探测器的探测器组通过导轨插入乏燃料组件 废燃料组件中的管孔，测量导管孔中伽马射线和中子检测器的伽马射线和中子辐射响应，通过将导管管位置处的伽马射线和中子辐射响应归一化为最大值 一组响应，并将导管位置处的伽马射线和中子响应的比例归一化，并将比率归一化为最大值，并根据这些归一化值产生三个特征，γ，中子和γ中子比， 并产生由这些签名组成的输出，这些签名可以指示引脚的可能转移 在乏燃料组件上。
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