-
1.发明授权Computer-implemented method and system for designing a nuclear reactor core which satisfies licensing criteria 有权用于设计满足许可标准的核反应堆核心的计算机实现方法和系统公开(公告)号：US08873698B2
公开(公告)日：2014-10-28
申请号：US11642871
申请日：2006-12-21
IPC分类号： G06F17/50 , G06G7/54 , G21D3/00 , G21C19/20 , G21C17/00 , G21D3/04 , G21D3/08 , G06F17/00 , G06G7/00
CPC分类号： G21C17/00 , G21C19/205 , G21D3/001 , G21D3/04 , G21D3/08 , G21D2003/002 , G21Y2002/201 , G21Y2002/202 , G21Y2002/203 , G21Y2002/304 , G21Y2004/40 , G21Y2004/403 , Y02E30/39
摘要： In a computer-implemented method of designing a nuclear reactor of a given reactor plant, an initial, test reactor core design is generated for the given plant based on a plurality of limits input by a user. The limits include a plurality of transient licensing constraints to be satisfied for operating the given plant. The method includes selecting, from a set of automated tools, one or more automated tools to evaluate the test core design, and operating one of more of selected automated tools to output data for display to the user. The displayed data is related to a core design that satisfies the limits inclusive of the transient licensing constraints.
摘要翻译： 在设计给定反应堆设备的核反应堆的计算机实现的方法中，基于由用户输入的多个限制，为给定设备产生初始的测试反应堆核心设计。 这些限制包括要为运行给定设备而满足的许多暂时许可限制。 该方法包括从一组自动化工具中选择一个或多个自动化工具来评估测试核心设计，以及操作多个所选择的自动化工具之一来输出用于显示给用户的数据。 显示的数据与满足临时许可限制的限制的核心设计相关。
-
2.发明授权Method and apparatus for evaluating a proposed solution to a constraint problem 失效用于评估拟议解决约束问题的方法和装置公开(公告)号：US07672815B2
公开(公告)日：2010-03-02
申请号：US11024844
申请日：2004-12-30
申请人： Mehdi Asgari , David Joseph Kropaczek , Gerald Dean Kvaall, Jr. , Roland Otto Jackson , Steven Barry Sutton , Christian Carlos Oyarzun
发明人： Mehdi Asgari , David Joseph Kropaczek , Gerald Dean Kvaall, Jr. , Roland Otto Jackson , Steven Barry Sutton , Christian Carlos Oyarzun
CPC分类号： G06N99/005
摘要： A method of evaluating constraint functions, the evaluation being based at least in part on a control blade movement criteria.
摘要翻译： 一种评估约束函数的方法，该评估至少部分地基于控制刀片运动标准。
-
3.发明授权Method of determining a fresh fuel bundle design for a core of a nuclear reactor 失效确定核反应堆核心的新鲜燃料束设计的方法公开(公告)号：US07574337B2
公开(公告)日：2009-08-11
申请号：US11024973
申请日：2004-12-30
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.
摘要翻译： 用于确定用于核反应堆的核心的新鲜燃料束设计的方法可以包括定义多个输入，包括用于评估N个束组中的每一个的一个或多个参考新鲜燃料束设计的用户定义的目标条件，以及产生响应 基于对每个N束组评估给定参考束设计的每个束的每个（i，j）棒位置进行单杆式变化的表面。 可以迭代搜索算法以使用所生成的响应面来评估在N个束组中的每一个上同时进行的多个杆型变化的给定组合，以确定满足用户 - 定义目标条件。
-
4.发明授权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：US07424412B2
公开(公告)日：2008-09-09
申请号：US11024974
申请日：2004-12-30
IPC分类号： G06F9/455
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。
-
5.发明授权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：US07461038B2
公开(公告)日：2008-12-02
申请号：US11312541
申请日：2005-12-21
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。
-
6.发明申请Method for improving energy output of a nuclear reactor, method for determining natural uranium blanket layer for a fuel bundle, and a fuel bundle having a variable blanket layer 有权用于改善核反应堆的能量输出的方法，用于确定用于燃料束的天然铀覆盖层的方法和具有可变覆盖层的燃料束公开(公告)号：US20080137792A1
公开(公告)日：2008-06-12
申请号：US11589723
申请日：2006-10-31
IPC分类号： G21C17/00
CPC分类号： G21C3/328 , G21C7/00 , G21D3/001 , G21Y2002/201 , G21Y2002/304 , G21Y2004/30 , Y02E30/38 , Y02E30/39
摘要： In a method for improving the energy generating output of a nuclear reactor containing one or more fuel rods in one or more fuel rod bundles while satisfying a maximum subcritical banked withdrawal position (MSBWP) reactivity limit, enrichments of individual fuel rods in an axial cross-section of a lattice being evaluated at the top of the fuel bundle are ranked, and the fuel pins of the highest ranked rod location in the lattice are replaced with natural uranium pins. A core simulation is then performed to determine whether there is any margin to a MSBWP reactivity limit. For each lower ranked candidate rod position, the pin replacing and core simulation functions are repeated until no rod location violates the MSBWP reactivity limit, so as to achieve a desired lattice design for the top of the fuel bundle.
摘要翻译： 在一种用于改善在一个或多个燃料棒束中包含一个或多个燃料棒的核反应堆的能量产生输出的方法中，同时满足最大亚临界分离取出位置（MSBWP）反应性极限，单个燃料棒在轴向交联中的富集， 对在燃料束顶部进行评估的格子的截面进行排序，并且用天然铀销代替格子中排列最高的杆位置的燃料销。 然后执行核心模拟以确定MSBWP反应性极限是否存在任何余地。 对于每个较低排名的候选杆位置，重复引脚替换和核心模拟功能，直到没有杆位置违反MSBWP反应极限，以便实现燃料束顶部的期望的晶格设计。
-
7.发明授权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：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
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。
-
8.发明授权Method for improving energy output of a nuclear reactor, method for determining natural uranium blanket layer for a fuel bundle, and a fuel bundle having a variable blanket layer 有权用于改善核反应堆的能量输出的方法，用于确定用于燃料束的天然铀覆盖层的方法和具有可变覆盖层的燃料束公开(公告)号：US08582713B2
公开(公告)日：2013-11-12
申请号：US11589723
申请日：2006-10-31
IPC分类号： G21C3/00
CPC分类号： G21C3/328 , G21C7/00 , G21D3/001 , G21Y2002/201 , G21Y2002/304 , G21Y2004/30 , Y02E30/38 , Y02E30/39
摘要： In a method for improving the energy generating output of a nuclear reactor containing one or more fuel rods in one or more fuel rod bundles while satisfying a maximum subcritical banked withdrawal position (MSBWP) reactivity limit, enrichments of individual fuel rods in an axial cross-section of a lattice being evaluated at the top of the fuel bundle are ranked, and the fuel pins of the highest ranked rod location in the lattice are replaced with pins containing natural uranium. A core simulation is then performed to determine whether there is any margin to a MSBWP reactivity limit. For each lower ranked candidate rod position, the pin replacing and core simulation functions are repeated until no rod location violates the MSBWP reactivity limit, so as to achieve a desired lattice design for the top of the fuel bundle.
摘要翻译： 在一种用于改善在一个或多个燃料棒束中包含一个或多个燃料棒的核反应堆的能量产生输出的方法中，同时满足最大亚临界分离取出位置（MSBWP）反应性极限，单个燃料棒在轴向交联中的富集， 对在燃料束顶部进行评估的格子的截面进行分级，将格子中排列最高的杆位置的燃料销替换为含有天然铀的销。 然后执行核心模拟以确定MSBWP反应性极限是否存在任何余地。 对于每个较低排名的候选杆位置，重复引脚替换和核心模拟功能，直到没有杆位置违反MSBWP反应极限，以便实现燃料束顶部的期望的晶格设计。
-
9.发明授权Method, arrangement and computer program for determining standardized rod types for nuclear reactors 有权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
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。
-
公开(公告)号：US06862329B1
公开(公告)日：2005-03-01
申请号：US10678171
申请日：2003-10-06
CPC分类号： G21D3/001 , G21C5/02 , G21C19/205 , G21Y2002/201 , G21Y2004/403 , Y02E30/40
摘要： According to the method, a reactor core is shut down during the operation cycle. One or more fuel bundles of the reactor core are then moved to new positions within the reactor core to increase a total energy, output of the reactor core as compared to continuing operation of the reactor core without the shutting down and moving steps.
摘要翻译： 根据该方法，在操作循环期间关闭反应堆芯。 然后将反应堆芯的一个或多个燃料束移动到反应堆堆芯内的新位置，以增加反应堆堆芯的总能量，输出与反应堆堆芯的连续运行相比，而不用关闭和移动步骤。
-
-
-
-
-
-
-
-
-
搜索结果
29 条记录 (耗时 0.023 秒)