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    Method, arrangement and computer program for generating database of fuel bundle designs for nuclear reactors
    1.
    发明申请
    Method, arrangement and computer program for generating database of fuel bundle designs for nuclear reactors 有权
    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：US20050015227A1

    公开(公告)日：2005-01-20

    申请号：US10879122

    申请日：2004-06-30

    申请人： David Kropaczek ,  Mehdi Asgari ,  Christian Oyarzun ,  Steven Sutton ,  William Russell ,  William Cline

    发明人： David Kropaczek ,  Mehdi Asgari ,  Christian Oyarzun ,  Steven Sutton ,  William Russell ,  William Cline

    IPC分类号： G21C17/00 ,  G06F17/10 ,  G06F17/50 ,  G06G7/54 ,  G06G7/62 ,  G21C1/00 ,  G21C3/32 ,  G21C5/00 ,  G21C19/20 ,  G21C23/00

    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。

    Method of determining margins to operating limits for nuclear reactor operation
    2.
    发明申请
    Method of determining margins to operating limits for nuclear reactor operation 有权
    确定核反应堆运行操作限值的利润率的方法

    公开(公告)号：US20070153958A1

    公开(公告)日：2007-07-05

    申请号：US11320919

    申请日：2005-12-30

    申请人： William Russell ,  Russell Fawcett ,  William Cline ,  David Kropaczek ,  Glen Watford ,  Lukas Trosman ,  Steven Sutton ,  Christian Oyarzun

    发明人： William Russell ,  Russell Fawcett ,  William Cline ,  David Kropaczek ,  Glen Watford ,  Lukas Trosman ,  Steven Sutton ,  Christian Oyarzun

    IPC分类号： G21C17/00

    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。

    Method and apparatus for evaluating robustness of proposed solution to constraint problem and considering robustness in developing a constraint problem solution
    6.
    发明申请
    Method and apparatus for evaluating robustness of proposed solution to constraint problem and considering robustness in developing a constraint problem solution 有权
    用于评估拟议解约束问题的鲁棒性的方法和装置，并考虑在制定约束问题解决方案中的鲁棒性

    公开(公告)号：US20070179919A1

    公开(公告)日：2007-08-02

    申请号：US11312541

    申请日：2005-12-21

    申请人： David Kropaczek ,  Christian Oyarzun ,  Steven Sutton ,  Mehdi Asgari

    发明人： David Kropaczek ,  Christian Oyarzun ,  Steven Sutton ,  Mehdi Asgari

    IPC分类号： G06F15/18

    CPC分类号： G05B13/024 ,  G21D3/001 ,  Y02E30/40

    摘要： In an embodiment of a method of evaluating robustness of a proposed solution to a constraint problem, operational output data for at least first and second modified versions of the proposed solution is generated. The first modified version has at least one control variable of the proposed solution perturbed in a first direction and the second modified version has the at least one control variable of the proposed solution perturbed in a second direction. At least a portion of the generated operation output data is then presented such as on a graphical user interface.

    摘要翻译： 在评估所提出的解决方案对约束问题的鲁棒性的方法的实施例中，生成所提出的解决方案的至少第一和第二修改版本的操作输出数据。 第一修改版本具有在第一方向上扰动的所提出的解决方案的至少一个控制变量，并且第二修改版本具有在第二方向上扰动的所提出的解决方案的至少一个控制变量。 生成的操作输出数据的至少一部分然后被呈现，例如在图形用户界面上。

    Method of determining nuclear reactor core design with reduced control blade density
    8.
    发明申请
    Method of determining nuclear reactor core design with reduced control blade density 有权
    确定核反应堆核心设计的方法，减少控制叶片密度

    公开(公告)号：US20050222833A1

    公开(公告)日：2005-10-06

    申请号：US11024974

    申请日：2004-12-30

    申请人： David Kropaczek ,  Mehdi Asgari ,  Richard McCord

    发明人： David Kropaczek ,  Mehdi Asgari ,  Richard McCord

    IPC分类号： G21C17/00 ,  G06F17/10 ,  G06F17/50 ,  G06G7/54 ,  G06G7/62 ,  G21C1/00 ,  G21C3/32 ,  G21C5/00 ,  G21C19/20 ,  G21C23/00

    CPC分类号： G21C5/00 ,  G21C17/00 ,  G21C19/20 ,  G21C19/205 ,  G21D3/001 ,  G21D2003/002 ,  G21Y2002/201 ,  G21Y2002/202 ,  G21Y2002/204 ,  G21Y2002/208 ,  G21Y2002/304 ,  G21Y2004/40 ,  Y02E30/39

    摘要： In the method, a reference core design is generated based on a defined set of limits. The set of limits may include a target hot excess reactivity constraint to be satisfied over a given core energy cycle and a given desired control blade definition that is set for the cycle. A reference core design is generated based on the defined limits. A unique subset of fresh fuel bundles is subject to an iterative improvement process including replacing, at each fuel location, at least one of the current fresh fuel bundles with at least one of the selected fresh fuel bundles, and simulating reactor operation on the reference core design to obtain a plurality of outputs to be ranked based on the defined set of limits. The highest ranked output may represent an accepted core design with set control blade definition that satisfies the target hot excess reactivity constraint.

    摘要翻译： 在该方法中，基于定义的限制集合生成参考核心设计。 所述限制的集合可以包括在给定的核心能量循环和为循环设置的给定的所需控制叶片定义时要满足的目标热过剩反应性约束。 基于定义的限制生成参考核心设计。 新鲜燃料束的独特子集受到迭代改进过程，包括在每个燃料位置使用所选择的新鲜燃料束中的至少一个代替当前新鲜燃料束中的至少一个，以及在参考核上模拟反应器操作 设计以基于所定义的限制集合来获得要排名的多个输出。 排名最高的产品可能代表一种被认可的核心设计，具有设定控制刀片定义，满足目标热过剩反应性约束。

    Method of determining a fresh fuel bundle design for a core of a nuclear reactor
    10.
    发明申请
    Method of determining a fresh fuel bundle design for a core of a nuclear reactor 失效

    公开(公告)号：US20060149514A1

    公开(公告)日：2006-07-06

    申请号：US11024973

    申请日：2004-12-30

    申请人： David Kropaczek ,  Mehdi Asgari ,  Matthew Jesse

    发明人： David Kropaczek ,  Mehdi Asgari ,  Matthew Jesse

    IPC分类号： G06G7/48

    CPC分类号： G21D3/001 ,  G21C7/36 ,  G21C17/00 ,  G21D2003/002 ,  Y02E30/39

    摘要： A method for determining a fresh fuel bundle design for a core of a nuclear reactor may include defining a plurality of inputs including user-defined target conditions for evaluating one or more reference fresh fuel bundle designs for each of N bundle groups, and generating a response surface based on making single rod-type changes in each (i,j) rod location of each bundle of a given reference bundle design being evaluated for each of the N bundle groups. A search algorithm may be iterated to evaluate a given combination of multiple rod-type changes made simultaneously across each of the N bundle groups using the generated response surface to determine an accepted fuel bundle design for each of the N bundle groups that satisfies the user-defined target conditions.