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    Exposure boost zone for boiling water reactor nuclear bundles
    1.
    发明授权
    Exposure boost zone for boiling water reactor nuclear bundles 有权
    沸水堆核反应堆暴露增压区

    公开(公告)号：US08953736B2

    公开(公告)日：2015-02-10

    申请号：US12756236

    申请日：2010-04-08

    申请人： Anthony P. Reese ,  Lukas Trosman ,  Gerald Dean Kvaall, Jr.

    发明人： Anthony P. Reese ,  Lukas Trosman ,  Gerald Dean Kvaall, Jr.

    IPC分类号： G21C3/32 ,  G21C3/326 ,  G21D3/00

    CPC分类号： G21C3/32 ,  G21C3/326 ,  G21C2003/3267 ,  G21D2003/002 ,  Y02E30/31 ,  Y02E30/38

    摘要： Disclosed are a fuel rod and a fuel bundle using the fuel rod. The fuel rod may include first enriched uranium in a boost zone of the fuel rod, wherein the boost zone may be arranged directly at a bottom of the fuel rod. The fuel rod may also include second enriched uranium in a second zone of the fuel rod, wherein the second zone is arranged over the boost zone. The fuel rod may also include natural uranium in a third zone of the fuel rod, wherein the third zone is arranged over the second zone. In this fuel rod, a percent of enrichment of the enriched uranium in the boost zone is at least one percent.

    摘要翻译： 公开了使用燃料棒的燃料棒和燃料束。 燃料棒可以包括在燃料棒的增压区中的第一浓缩铀，其中增压区可以直接布置在燃料棒的底部。 燃料棒还可以包括在燃料棒的第二区域中的第二浓缩铀，其中第二区域布置在增压区域的上方。 燃料棒还可以包括在燃料棒的第三区域中的天然铀，其中第三区域布置在第二区域之上。 在该燃料棒中，增压区中浓缩铀浓度的百分比至少为1％。

    Nuclear reactor reload licensing analysis system and method
    2.
    发明授权
    Nuclear reactor reload licensing analysis system and method 有权
    核反应堆重装许可证分析制度和方法

    公开(公告)号：US07426458B2

    公开(公告)日：2008-09-16

    申请号：US11027580

    申请日：2004-12-30

    申请人： Charles E. Horton ,  James E. Fawks ,  Carter Couser Tarrer ,  Gary D. Galloway

    发明人： Charles E. Horton ,  James E. Fawks ,  Carter Couser Tarrer ,  Gary D. Galloway

    IPC分类号： G06G7/48

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

    摘要： A system and computer implemented method for automatically performing reload licensing analysis of a nuclear reactor and preparing and generating a reload licensing report. The system and method include collecting input data and processing a plurality of nuclear reactor analysis modules. Each of the nuclear reactor analysis modules receives analysis module input data and generates analysis output data. The analysis module input data is based at least in part on the collected input data. The method also includes verifying at least one analysis output data from one nuclear reactor analysis module by comparing the analysis output data to predetermined analysis output data for the one nuclear reactor analysis module. The method further includes generating a reload licensing report for the nuclear reactor as a function of the analysis output data from two or more nuclear reactor analysis modules.

    摘要翻译： 一种系统和计算机实现的方法，用于自动执行核反应堆的重新加载许可分析，并准备和生成重新载入许可报告。 该系统和方法包括收集输入数据并处理多个核反应堆分析模块。 每个核反应堆分析模块接收分析模块输入数据并生成分析输出数据。 分析模块输入数据至少部分地基于所收集的输入数据。 该方法还包括通过将分析输出数据与一个核反应堆分析模块的预定分析输出数据进行比较来验证来自一个核反应堆分析模块的至少一个分析输出数据。 该方法还包括根据来自两个或多个核反应堆分析模块的分析输出数据生成核反应堆的重新装载许可报告。

    Method of establishing a nuclear reactor core fuel assembly loading pattern
    5.
    发明授权
    Method of establishing a nuclear reactor core fuel assembly loading pattern 有权
    建立核反应堆堆芯燃料装配模式的方法

    公开(公告)号：US06931090B2

    公开(公告)日：2005-08-16

    申请号：US10374691

    申请日：2003-02-25

    申请人： Yung-An Chao ,  Shengyi Si ,  Frank D. Popa

    发明人： Yung-An Chao ,  Shengyi Si ,  Frank D. Popa

    IPC分类号： G21C21/00 ,  G21C5/00 ,  G21C5/02 ,  G21C7/00 ,  G21C17/00 ,  G21C19/20 ,  G21C19/00

    CPC分类号： G21C5/00 ,  G21C5/02 ,  G21C7/00 ,  G21C19/205 ,  G21D3/001 ,  G21D2003/002 ,  G21Y2002/201 ,  G21Y2002/304 ,  G21Y2004/40 ,  G21Y2004/403 ,  Y02E30/39

    摘要： All possible loading patterns for a nuclear reactor core are searched and optimized for compliance with design constraints. The fuel inventory is divided into a few batches according to coarse levels of reactivity. A recursive enumeration process identifies patterns meeting selected core position constraints, which can be user modified to adjust the search space size. For the batch loading patterns satisfying the constraints, the batches are divided into several smaller batches. A sensitivity matrix linearizing the relationship between fuel assembly position and the depletion model is processed through mixed integer linear programming with branching and bounding to identify an optimal daughter loading pattern. The process is repeated through several levels of batch refinement and selection of optimal daughter patterns, including a level where burnable absorbers are assigned to feed assemblies, until the individual fuel assembly level is reached. The multiple optimal patterns remaining provide a range of solutions.

    摘要翻译： 搜索和优化核反应堆核心的所有可能的加载模式，以符合设计约束。 燃料库存根据粗略的反应性分为几批。 递归计数过程确定满足选定核心位置约束的模式，可以通过用户修改来调整搜索空间大小。 对于满足约束的批量加载模式，批次分为几个较小的批次。 通过具有分支和边界的混合整数线性规划来处理线性化燃料组装位置和耗尽模型之间的关系的灵敏度矩阵，以识别最佳的子载荷模式。 该过程通过几个级别的批次精炼和最佳子模式的选择重复，包括将可燃吸收器分配给进料组件的水平，直到达到单独的燃料组件水平。 剩余的多种最佳模式提供了一系列解决方案。

    Computer Implemented Method for Modelizing A Nuclear Reactor Core and a Corresponding Computer Program Product
    7.
    发明申请
    Computer Implemented Method for Modelizing A Nuclear Reactor Core and a Corresponding Computer Program Product 有权
    计算机实现核反应堆核心建模方法和相应的计算机程序产品

    公开(公告)号：US20110046930A1

    公开(公告)日：2011-02-24

    申请号：US12857164

    申请日：2010-08-16

    申请人： René Van Geemert

    发明人： René Van Geemert

    IPC分类号： G06F17/11 ,  G06F17/16

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

    摘要： A computer implemented method for modelizing a nuclear reactor core, including the steps of: partitioning the core in cubes to constitute nodes of a grid for computer implemented calculation, calculating neutron flux by using an iterative solving procedure of at least one eigensystem, the components of an iterant of the eigensystem corresponding either to a neutron flux, to a neutron outcurrent or to a neutron incurrent, for a respective cube to be calculated.The neutrons are sorted in a plurality of neutron energy groups, and the eigensystem iterative solving procedure includes a substep of conditioning the eigensystem into a restricted eigensystem corresponding to the eigensystem for a selection of some neutron energy groups.

    摘要翻译： 一种用于对核反应堆核心进行建模的计算机实现的方法，包括以下步骤：将立方体中的核分割成用于计算机实现的计算的网格的节点，通过使用至少一个特征系统的迭代求解程序来计算中子通量， 对于要计算的相应立方体，特征系统的迭代对应于中子通量，中子外流或中子入射。 中子在多个中子能量组中分类，并且特征系统迭代求解过程包括将特征系统调节成对应于特征系统的受限同源系统的子步骤，用于选择一些中子能量组。

    Method for computer modeling the core of a nuclear reactor
    10.
    发明申请
    Method for computer modeling the core of a nuclear reactor 有权
    计算机模拟核反应堆核心的方法

    公开(公告)号：US20060184286A1

    公开(公告)日：2006-08-17

    申请号：US11319000

    申请日：2005-12-27

    申请人： Rainer Boer ,  Lothar Hetzelt ,  Horst-Dieter Kiehlmann ,  Hans-Joachim Winter

    发明人： Rainer Boer ,  Lothar Hetzelt ,  Horst-Dieter Kiehlmann ,  Hans-Joachim Winter

    IPC分类号： G05D11/00

    CPC分类号： G21C5/00 ,  G21C7/00 ,  G21C21/00 ,  G21D3/001 ,  G21D2003/002 ,  G21Y2002/201 ,  G21Y2002/202 ,  G21Y2002/204 ,  G21Y2002/304 ,  G21Y2004/40 ,  Y02E30/39

    摘要： In a computer modeling method for the core of a nuclear reactor the core is divided into a plurality of primary grids in the form of coarse mesh cells. A sub-section of the core relating to at least one grid is assigned to that grid. The sub-section includes that grid and a buffer zone that surrounds the grid horizontally and contains at least the grid that lies immediately adjacent to the first grid. The sub-section is sub-divided into a plurality of secondary grids—fine mesh cells—that are smaller than the primary grids. In a first computing step, a model of the core is calculated using a nodal calculation method, based on a respective dataset that is assigned to each primary grid. In a second computing step, a respective second dataset is assigned to each secondary grid of a sub-section and a model is then calculated for the sub-section, based on the dataset and the flows on the border of the sub-section that have been calculated in the first computing step.

    摘要翻译： 在用于核反应堆的核心的计算机建模方法中，核心被分为多个粗网格细胞形式的主网格。 与至少一个网格相关的核心的子部分被分配给该网格。 该子部分包括网格和缓冲区，其横向包围网格，并且至少包含紧邻第一网格的网格。 该子部分被细分为多个次网格 - 细网格单元 - 小于一次网格。 在第一计算步骤中，基于分配给每个主网格的相应数据集，使用节点计算方法来计算核心的模型。 在第二计算步骤中，将相应的第二数据集分配给子部分的每个次级网格，然后基于数据集和具有所述子部分的子部分的边界上的流动来为子部分计算模型 在第一计算步骤中计算。