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1. 发明授权

US07636652B2 Method and apparatus for facilitating recovery of nuclear fuel from a fuel pool 失效
标题翻译：便于从燃料池回收核燃料的方法和装置
公开(公告)号：US07636652B2
公开(公告)日：2009-12-22
申请号：US10678170
申请日：2003-10-06
申请人： David Joseph Kropaczek , Steven Barry Sutton , Christian Carlos Oyarzun , Carey Reid Merritt , John Dean Fuller , William Earl Russell, II , Margaret Estelle Harding
发明人： David Joseph Kropaczek , Steven Barry Sutton , Christian Carlos Oyarzun , Carey Reid Merritt , John Dean Fuller , William Earl Russell, II , Margaret Estelle Harding
IPC分类号： G06G7/48 , G21C19/00
CPC分类号： G21D3/001 , G21C17/06 , G21C19/18 , G21C19/205 , G21Y2002/201 , G21Y2002/202 , G21Y2002/205 , G21Y2002/208 , G21Y2004/40 , Y02E30/40
摘要： The apparatus for creating and editing a nuclear reactor core template includes a graphical user interface and a processor controlling the graphical user interface to allow a user to selectively populate a loading map with fuel bundles residing in at least one fuel pool.
摘要翻译：用于创建和编辑核反应堆核心模板的装置包括图形用户界面和控制图形用户界面的处理器，以允许用户选择性地填充驻留在至少一个燃料池中的燃料束的装载图。

2. 发明授权

US07941305B2 Method and apparatus for moving nuclear fuel 有权
标题翻译：移动核燃料的方法和装置
公开(公告)号：US07941305B2
公开(公告)日：2011-05-10
申请号：US12641750
申请日：2009-12-18
申请人： David Joseph Kropaczek , Steven Barry Sutton , Christian Carlos Oyarzun , Carey Reid Merritt , John Dean Fuller , William Earl Russell, II , Margaret Estelle Harding
发明人： David Joseph Kropaczek , Steven Barry Sutton , Christian Carlos Oyarzun , Carey Reid Merritt , John Dean Fuller , William Earl Russell, II , Margaret Estelle Harding
IPC分类号： G06G7/48 , G21C19/00
CPC分类号： G21D3/001 , G21C17/06 , G21C19/18 , G21C19/205 , G21Y2002/201 , G21Y2002/202 , G21Y2002/205 , G21Y2002/208 , G21Y2004/40 , Y02E30/40
摘要： The apparatus for creating and editing a nuclear reactor core template includes a graphical user interface and a processor controlling the graphical user interface to allow a user to selectively populate a loading map with fuel bundles residing in at least one fuel pool.
摘要翻译：用于创建和编辑核反应堆核心模板的装置包括图形用户界面和控制图形用户界面的处理器，以允许用户选择性地填充驻留在至少一个燃料池中的燃料束的装载图。

3. 发明授权

US07222061B2 Method and arrangement for developing rod patterns in nuclear reactors 有权
标题翻译：在核反应堆中开发棒图的方法和布置
公开(公告)号：US07222061B2
公开(公告)日：2007-05-22
申请号：US10321441
申请日：2002-12-18
申请人： William Earl Russell, II , David Joseph Kropaczek , Steven Barry Sutton , Christian Carlos Oyarzun , William Charles Cline , Carey Reid Merritt
发明人： William Earl Russell, II , David Joseph Kropaczek , Steven Barry Sutton , Christian Carlos Oyarzun , William Charles Cline , Carey Reid Merritt
IPC分类号： G06G7/54 , G21C7/00 , G21C17/00 , G21C23/00 , G09B9/00 , G09B19/00 , G09B25/00 , G06F15/16 , G06F11/30 , G06F12/14
CPC分类号： G21D3/001 , G21C5/02 , G21C7/00 , G21D2003/002 , G21Y2002/201 , G21Y2004/40 , G21Y2004/403 , Y02E30/39
摘要： In the method, a set of limits applicable to a test rod pattern design are defined, and a sequence strategy for positioning one or more subsets of the test rod pattern design is established. Reactor operation on a subset of the test rod pattern design, which may be a subset of fuel bundles in a reactor core for example, is simulated to produce a plurality of simulated results. The simulated results are compared against the limits, and data from the comparison is provided to indicate whether any of the limits were violated by the test rod pattern design during the simulation. A designer or engineer may use the data to determine which operator parameters need to be adjusted (e.g., control blade notch positions for example) in order to create a derivative rod pattern design for simulation, and eventually perfect a rod pattern design for a particular core.
摘要翻译：在该方法中，定义了适用于测试棒图案设计的一组限制，并且建立了用于定位测试棒图案设计的一个或多个子集的序列策略。模拟试验棒图案设计的子集上的反应器操作，其可以是例如反应堆芯中的燃料束的子集，以产生多个模拟结果。将模拟结果与极限进行比较，并提供比较数据，以指示在模拟期间是否有任何限制被测试棒图案设计所违反。设计师或工程师可以使用数据来确定哪些操作者参数需要调整（例如，例如控制刀片凹口位置），以便创建用于模拟的导数棒图案设计，并且最终完善特定芯的棒图案设计。

4. 发明授权

US07231333B2 Method and arrangement for developing core loading patterns in nuclear reactors 有权
标题翻译：在核反应堆中开发核心装载模式的方法和安排
公开(公告)号：US07231333B2
公开(公告)日：2007-06-12
申请号：US10401602
申请日：2003-03-31
申请人： William Earl Russell, II , David Joseph Kropaczek , Steven Barry Sutton , William Charles Cline , Christian Carlos Oyarzun , Glen Alan Watford , Carey Reid Merritt
发明人： William Earl Russell, II , David Joseph Kropaczek , Steven Barry Sutton , William Charles Cline , Christian Carlos Oyarzun , Glen Alan Watford , Carey Reid Merritt
IPC分类号： G06F9/455
CPC分类号： G21C5/02 , G21C19/205 , G21D3/001 , G21Y2002/201 , G21Y2002/202 , G21Y2002/304 , G21Y2004/40 , Y02E30/40
摘要： In the method, a set of limits applicable to a core may be defined, and a test core loading pattern design, to be used for loading the core, may be determined based on the limits. Reactor operation on at least a subset of the core may be simulated to produce a plurality of simulated results. The simulated results may be compared against the limits, and data from the comparison may indicate whether any of the limits were violated by the core during the simulation. A designer or engineer may use the data to modify the test core loading pattern, creating one or more derivative core loading pattern design(s) for simulation and eventual perfection as an acceptable core loading pattern design for the core.
摘要翻译：在该方法中，可以定义适用于芯的一组限制，并且可以基于限制来确定用于装载芯的测试芯加载模式设计。可以对核心的至少一个子集进行反应器操作，以产生多个模拟结果。模拟结果可以与限制进行比较，并且来自比较的数据可以指示模拟期间核心是否有任何限制被违反。设计师或工程师可以使用数据来修改测试核心加载模式，创建一个或多个用于模拟和最终完善的衍生核心加载模式设计，作为核心的可接受的核心加载模式设计。

5. 发明授权

US07337099B2 Method, arrangement and computer program for generating database of fuel bundle designs for nuclear reactors 有权
标题翻译：用于生成核反应堆燃料束设计数据库的方法，安排和计算机程序
公开(公告)号：US07337099B2
公开(公告)日：2008-02-26
申请号：US10879122
申请日：2004-06-30
申请人： David Joseph Kropaczek , Mehdi Asgari , Christian Carlos Oyarzun , Steven Barry Sutton , William Earl Russell, II , William Charles Cline
发明人： David Joseph Kropaczek , Mehdi Asgari , Christian Carlos Oyarzun , Steven Barry Sutton , William Earl Russell, II , William Charles Cline
IPC分类号： G06F7/60 , G06F17/10 , G21C19/00 , G09B25/00
CPC分类号： G21D3/001 , G21C3/00 , G21C19/205 , G21D2003/002 , G21Y2002/30 , G21Y2004/401 , Y02E30/40
摘要： A method, arrangement and computer program is described for generating a database of selectable fresh fuel bundle designs usable in one or more nuclear reactors. In an example, an initial population of candidate fresh fuel bundle designs may be generated and a set of rod-type changes to make to a given candidate in the initial population may be established. A given candidate fresh fuel bundle may be modified by making at least one rod-type change from the set therein. A core loaded with the modified bundle design may be simulated to generate bundle performance outputs. The bundle performance outputs may be ranked based on a plurality of user-input limits. The modified candidate fresh fuel bundle design may be stored, if the bundle performance outputs meet, or are within an accepted margin to, the user-input limits, so as to generate the database.
摘要翻译：描述了用于生成可用于一个或多个核反应堆中的可选择的新鲜燃料束设计的数据库的方法，布置和计算机程序。在一个示例中，可以生成候选新鲜燃料束设计的初始种群，并且可以建立对初始种群中的给定候选物进行的一组条形变化。给定的候选新鲜燃料束可以通过从其中的组中进行至少一个棒式改变来改变。可以模拟加载修改的捆绑设计的核心，以生成捆绑包性能输出。可以基于多个用户输入限制对捆绑性能输出进行排名。如果捆绑性能输出满足或在用户输入限制内的可接受余量内，则可以存储修改后的候选新鲜燃料束设计，以便生成数据库。

6. 发明授权

US07366273B2 Method of determining margins to operating limits for nuclear reactor operation 有权
标题翻译：确定核反应堆运行操作限值的利润率的方法
公开(公告)号：US07366273B2
公开(公告)日：2008-04-29
申请号：US11320919
申请日：2005-12-30
申请人： William Earl Russell, II , Russell Morgan Fawcett , William Charles Cline , David Joseph Kropaczek , Glen A. Watford , Lukas Trosman , Steven Barry Sutton , Christian Carlos Oyarzun
发明人： William Earl Russell, II , Russell Morgan Fawcett , William Charles Cline , David Joseph Kropaczek , Glen A. Watford , Lukas Trosman , Steven Barry Sutton , Christian Carlos Oyarzun
IPC分类号： G21C7/36
CPC分类号： G21C17/00 , G21D3/001 , G21Y2002/201 , G21Y2002/304 , G21Y2004/40 , Y02E30/40
摘要： In a method of determining an operating margin to a given operating limit in a nuclear reactor, operational plant data from an on-line nuclear reactor plant is accessed, and reactor operation is simulated off-line using the operational plant data to generate predicted dependent variable data representative of the given operating limit. The predicted dependent variable data is normalized for evaluation with normalized historical dependent variable data from stored operating cycles of plants having a similar plant configuration to the on-line plant. A time-dependent average bias and a time-dependent uncertainty value for the predicted dependent variable data are determined using the normalized historical dependent variable data, and a risk-tolerance level for the on-line plant is obtained. An operating margin to the given operating limit is determined based on the determined time time-dependent average bias value and time-dependent uncertainty value so as to satisfy the risk-tolerance level of the evaluated plant.
摘要翻译：在确定核反应堆中给定运行极限的运行余量的方法中，访问来自在线核反应堆设备的运行设备数据，并使用运行设备数据离线模拟反应堆运行，以产生预测的因变量数据代表给定的操作限制。将预测的因变量数据归一化以用来自具有类似工厂配置的植物的存储操作周期与在线植物的归一化历史因变量数据进行评估。使用归一化的历史因变量数据确定预测的因变量数据的时间依赖平均偏差和时间依赖的不确定性值，并且获得在线工厂的风险容忍水平。基于确定的时间依赖平均偏差值和时间依赖不确定度值确定给定操作限制的操作余量，以满足评估工厂的风险容忍水平。

7. 发明授权

US07266481B2 Method, arrangement and computer program for determining standardized rod types for nuclear reactors 有权
标题翻译：确定核反应堆标准杆类型的方法，安排和计算机程序
公开(公告)号：US07266481B2
公开(公告)日：2007-09-04
申请号：US10879358
申请日：2004-06-30
申请人： David Joseph Kropaczek , Mehdi Asgari , Christian Carlos Oyarzun , Steven Barry Sutton , William Earl Russell, II , William Charles Cline
发明人： David Joseph Kropaczek , Mehdi Asgari , Christian Carlos Oyarzun , Steven Barry Sutton , William Earl Russell, II , William Charles Cline
IPC分类号： G06G7/48 , G06F17/10
CPC分类号： G21D3/001 , G21C3/00 , G21C19/205 , G21Y2002/30 , G21Y2004/40 , Y02E30/40
摘要： A method, arrangement and computer program is described for determining a set of standardized rod types for use in a nuclear reactor core. The method may include defining a set of rod type-related limits, and determining, based on the limits, an initial population of rod types to be evaluated for use in cores of a selected number of nuclear reactor plants. Based on the initial population of rod types a database of selectable fresh fuel bundle designs applicable to the one or more cores may be generated. Bundle data related to at least a subset of the selectable fresh fuel bundle designs may be retrieved from the database, and a target number of rod types may be selected from the initial population based on the retrieved bundle data as the set of standardized rod types.
摘要翻译：描述了用于确定在核反应堆堆芯中使用的一组标准的杆类型的方法，布置和计算机程序。该方法可以包括定义一组杆类型相关的限制，并且基于该限制确定待评估的杆类型的初始种群以用于选定数量的核反应堆设备的核心。基于杆类型的初始种群，可以生成可应用于一个或多个核的可选择的新鲜燃料束设计的数据库。可以从数据库检索与可选择的新鲜燃料束设计的至少一个子集相关的捆绑数据，并且可以基于所检索的捆绑数据作为标准化杆类型的集合，从初始种群中选择目标数量的杆类型。

8. 发明授权

US07693249B2 Method of improving nuclear reactor performance 失效
标题翻译：提高核反应堆性能的方法
公开(公告)号：US07693249B2
公开(公告)日：2010-04-06
申请号：US10355013
申请日：2003-01-31
申请人： David Joseph Kropaczek , William Earl Russell, II
发明人： David Joseph Kropaczek , William Earl Russell, II
IPC分类号： G21C7/36
CPC分类号： G21D3/001 , G21D3/08 , G21Y2002/201 , G21Y2004/30 , Y02E30/40
摘要： The method of improving nuclear reactor performance involves generating an operational solution for a nuclear reactor based on a constraint accounting for a problem with operation of the nuclear reactor. The generated operational solution can then be implemented at the nuclear reactor.
摘要翻译：改进核反应堆性能的方法涉及到根据核反应堆运行问题的约束产生核反应堆的运行解决方案。所产生的操作解决方案然后可以在核反应堆实施。

9. 发明授权

US09047995B2 Method and system for designing a nuclear reactor core for uprated power operations 有权
标题翻译：用于设计用于升级电力运行的核反应堆堆芯的方法和系统
公开(公告)号：US09047995B2
公开(公告)日：2015-06-02
申请号：US11585965
申请日：2006-10-25
申请人： David Joseph Kropaczek , William Earl Russell, II
发明人： David Joseph Kropaczek , William Earl Russell, II
IPC分类号： G21C19/19 , G21D3/00 , G21C5/02 , G21C7/00
CPC分类号： G21D3/001 , G21C5/02 , G21C7/00 , G21Y2002/201 , G21Y2002/304 , G21Y2004/30 , G21Y2004/40 , Y02E30/39
摘要： In a method of designing a nuclear reactor core for uprated power operations, a set of constraints are inputted to be satisfied for uprated power operations, and a test reactor core design is generated based on the constraints. One or more automated tools may be selected from a set of automated tools to evaluate the test core design against the constraints. The selected tool may then be operated. Operation of the selected automated tool includes simulating reactor operation with the test core design, based on the constraints, to produce a plurality of outputs, comparing the outputs against the constraints, and providing data indicating constraints that were violated by the test core design during the simulation, based on the comparison. One or more of the automated tools are iterated until a test core design meets all constraints for uprated power operations, thereby representing an acceptable power uprate core design.
摘要翻译：在设计用于上升功率操作的核反应堆堆芯的方法中，输入一组约束以满足上升功率操作，并且基于约束产生测试反应堆堆芯设计。可以从一组自动化工具中选择一个或多个自动化工具，以根据约束来评估测试核心设计。然后可以操作所选择的工具。所选择的自动化工具的操作包括基于约束来模拟具有测试核心设计的反应堆操作，以产生多个输出，将输出与约束进行比较，以及提供指示在测试核心设计期间违反的约束的数据仿真，基于比较。一个或多个自动化工具被迭代，直到测试核心设计满足上升功率操作的所有约束，从而表示可接受的上电核心设计。

10. 发明授权

US07555092B2 System and method for continuous optimization of control-variables during operation of a nuclear reactor 失效
标题翻译：在核反应堆运行期间连续优化控制变量的系统和方法
公开(公告)号：US07555092B2
公开(公告)日：2009-06-30
申请号：US10608086
申请日：2003-06-30
申请人： William Earl Russell, II , David Joseph Kropaczek , Glen Alan Watford
发明人： William Earl Russell, II , David Joseph Kropaczek , Glen Alan Watford
IPC分类号： G21C7/36
CPC分类号： G21D3/001 , G21D3/08 , G21Y2002/201 , G21Y2004/30 , G21Y2004/403 , Y02E30/40
摘要： A system and method is provided for a continual updating of the optimization of multiple operational control-variables during the operation of a nuclear reactor over a plurality of fuel cycles. A networked computer system includes one or more hosts programmed to execute an optimization process to identify and make changes in quantitative values of operational control-variables that result in improved efficiency and operational flexibility. Optimization and updating of operational control-variables may proceed selectively under manual control for inputting specific optimization constraints and reactor state-point information or may proceed autonomously through a repetitive performing of the optimization process based upon a predetermined user-defined strategy stored on the network. Communications between users and networked processors is facilitated by use of a TCP/IP server connected to the Internet so that portions of the optimization process may be conducted contemporaneously at remote locations and/or the results made accessible to users via conventional browser enabled computers.
摘要翻译：提供了一种用于在多个燃料循环期间在核反应堆的操作期间持续更新多个操作控制变量的优化的系统和方法。联网计算机系统包括一个或多个主机，其被编程为执行优化过程以识别和改变操作控制变量的定量值，从而提高效率和操作灵活性。操作控制变量的优化和更新可以在用于输入特定优化约束和反应器状态点信息的手动控制下选择性地进行，或者可以基于存储在网络上的预定用户定义的策略通过重复执行优化过程自主进行。通过使用连接到因特网的TCP / IP服务器来促进用户和网络处理器之间的通信，使得优化过程的一部分可以在远程位置同时进行和/或通过经常浏览器启用的计算机使用户可访问的结果。

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