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    NUCLEAR CROSS SECTION DOPPLER BROADENING METHOD AND APPARATUS
    1.
    发明公开
    NUCLEAR CROSS SECTION DOPPLER BROADENING METHOD AND APPARATUS 审中-公开

    公开(公告)号：US20240331885A1

    公开(公告)日：2024-10-03

    申请号：US17920700

    申请日：2021-03-30

    申请人： Changyuan LIU

    发明人： Changyuan LIU

    IPC分类号： G21D3/00

    CPC分类号： G21D3/002

    摘要： The present invention relates to a nuclear cross section Doppler broadening method and device. The method includes: discretizing a product F(x,θ) of an average reaction cross section function σ(E,T) and an energy E on grids equally divided on a square roll N of the energy as Fkc(θ), where incident particles have mass m and energy E, target particles have mass M and Maxwellian energy distribution under a temperature T, and E(x,θ)=Eσ(E,T), Fkc(θ)=F(xk,θ), k=0,1, . . . N−1, x=√{square root over (E)}, and c are discrete superscript symbols; expanding the product F(x,θ) of the average reaction cross section function and the energy on a group of orthogonal function sets, an expansion coefficient is {circumflex over (f)}j(θ), and j is an index of the orthogonal function sets, where for the discretized product Fkc(θ) of the average reaction cross section function and the energy, an orthogonal function expansion coefficient thereof is {circumflex over (f)}jc(θ)≈{circumflex over (f)}j(θ), based on the product F(x,0) of the average reaction cross section function and the energy under a 0 K temperature, obtaining a group of coefficient weights {circumflex over (f)}jc(0), where {circumflex over (f)}jc(θ) is a function of {circumflex over (f)}jc(0); and representing F(x,θ) as a sum of an orthogonal function of the group of coefficient weights, using the group of coefficient weights {circumflex over (f)}jc(θ), calculating F(x,θ), and obtaining an average reaction cross section σ(E,T).

    METHODS AND SYSTEMS FOR NUCLEAR REACTOR DESIGN USING FUEL-CLADDING THERMO-MECHANICS ANALYSIS
    2.
    发明公开
    METHODS AND SYSTEMS FOR NUCLEAR REACTOR DESIGN USING FUEL-CLADDING THERMO-MECHANICS ANALYSIS 审中-公开

    公开(公告)号：US20240304350A1

    公开(公告)日：2024-09-12

    申请号：US18572666

    申请日：2022-06-24

    申请人： GEORGIA TECH RESEARCH CORPORATION

    发明人： Anna S. ERICKSON ,  Nicholas J. FASSINO

    IPC分类号： G21D3/00

    CPC分类号： G21D3/002

    摘要： Described herein are methods for analyzing an operating envelope of a nuclear reactor. An example method includes obtaining operating envelope parameters associated with a first reactor core by performing a plurality of thermo-hydraulic and thermo-mechanical calculations for the first reactor core, where the first reactor core includes a first fuel-cladding material and has a first fuel pin geometry; obtaining operating envelope parameters associated with a second reactor core by performing a plurality of thermo-hydraulic and thermo-mechanical calculations for the second reactor core, where the second reactor core includes a second fuel-cladding material and has a second fuel pin geometry; and assessing an expandable operating envelope by comparing the respective operating envelope parameters associated with the first reactor core and the second reactor core, where the first and second fuel-cladding materials are different materials. The example method can include iteratively performing the steps described herein.

    METHOD OF SYNTHESIZING AXIAL POWER DISTRIBUTIONS OF NUCLEAR REACTOR CORE USING NEURAL NETWORK CIRCUIT AND IN-CORE PROTECTION SYSTEM (ICOPS) USING THE SAME
    3.
    发明申请
    METHOD OF SYNTHESIZING AXIAL POWER DISTRIBUTIONS OF NUCLEAR REACTOR CORE USING NEURAL NETWORK CIRCUIT AND IN-CORE PROTECTION SYSTEM (ICOPS) USING THE SAME 审中-公开
    使用神经网络电路和内核保护系统（ICOPS）合成核反应堆核心轴功率分布的方法

    公开(公告)号：US20160180976A1

    公开(公告)日：2016-06-23

    申请号：US14857712

    申请日：2015-09-17

    申请人： KEPCO Nuclear Fuel Co., Ltd

    发明人： Young Ho Park ,  Young Baek Kim ,  Dong Soo Kim ,  Do Young Oh

    IPC分类号： G21C17/06 ,  G21D3/10 ,  G06N3/08 ,  G06G7/54

    CPC分类号： G21C17/06 ,  G06G7/54 ,  G06N3/088 ,  G21D3/00 ,  G21D3/002 ,  G21D3/10 ,  Y02E30/39

    摘要： There are provided a method of synthesizing axial power distributions of a nuclear reactor core using a neural network circuit and an in-core protection system (ICOPS) using the same, in which using the neural network circuit including an input layer, an output layer, and at least one hidden layer, each layer being configured with at least one node, each node of one layer being connected to nodes of the other layers, node-to-node connections being made with connection weights varied based on a learning result, optimum connection weights between the respective nodes constituting the neural network circuit are determined through learning based on various core design data applied to the design of a nuclear reactor core of a nuclear power plant, and axial power distributions of the nuclear reactor core are synthesized based on ex-core flux detector signals measured by ex-core neutron flux detectors during operation of a nuclear reactor, so that the initial time required to perform a start-up test of the nuclear reactor can be reduced since basic data for synthesizing axial power distributions need not be separately measured in the start-up test of the nuclear reactor contrary to a conventional ICOPS, thereby improving the economic efficiency of the nuclear power plant, and so that overall nuclear reactor core design data can be used rather than actual measurement data in the start-up test (i.e., at the beginning of a period of nuclear fuel), thereby more accurately replicating axial power distributions of the nuclear reactor core throughout the overall period of the nuclear fuel.

    摘要翻译： 提供了一种使用神经网络电路和使用其的核心保护系统（ICOPS）来合成核反应堆堆芯的轴向功率分布的方法，其中使用神经网络电路包括输入层，输出层， 和至少一个隐藏层，每个层被配置有至少一个节点，一个层的每个节点连接到其他层的节点，节点到节点连接是用连接权重进行的，所述连接权重基于学习结果而变化，最优 通过基于应用于核电站核反应堆核心设计的各种核心设计数据的学习来确定构成神经网络电路的各个节点之间的连接权重，并且基于前者合成核反应堆堆芯的轴向功率分布 在核反应堆运行期间由核心中子通量检测器测量的核磁通检测器信号，使得执行起始 - 可以减少核反应堆的上升试验，因为与常规ICOPS相反，在核反应堆的启动试验中不需要单独测量用于合成轴向功率分布的基础数据，从而提高核电厂的经济效率， 因此可以使用整个核反应堆核心设计数据而不是启动试验中的实际测量数据（即在核燃料周期开始时），从而更准确地复制整个核反应堆核心的轴向功率分布 整个核燃料时期。

    METHOD OF SYNTHESIZING AXIAL POWER DISTRIBUTIONS OF NUCLEAR REACTOR CORE USING NEURAL NETWORK CIRCUIT AND IN-CORE MONITORING SYSTEM (ICOMS) USING THE SAME
    6.
    发明申请
    METHOD OF SYNTHESIZING AXIAL POWER DISTRIBUTIONS OF NUCLEAR REACTOR CORE USING NEURAL NETWORK CIRCUIT AND IN-CORE MONITORING SYSTEM (ICOMS) USING THE SAME 审中-公开
    使用神经网络电路和内核监测系统（ICOMS）合成核反应堆核心轴功率分布的方法

    公开(公告)号：US20160300630A1

    公开(公告)日：2016-10-13

    申请号：US14857740

    申请日：2015-09-17

    申请人： KEPCO Nuclear Fuel Co., Ltd

    发明人： Young Ho Park ,  Young Baek Kim ,  Hye Jin Kim ,  Young Jae Choi ,  Kyoung Woo Shim

    IPC分类号： G21C17/01 ,  G06N3/08 ,  G06F17/14 ,  G06N3/04

    CPC分类号： G06N3/084 ,  G21C17/10 ,  G21D3/002

    摘要： There are provided a method of synthesizing axial power distributions of a nuclear reactor core using a neural network circuit and an in-core monitoring system (ICOMS) using the same, in which using the neural network circuit including an input layer, an output layer, and at least one hidden layer, each layer being configured with at least one node, each node of one layer being connected to nodes of the other layers, node-to-node connections being made with connection weights varied based on a learning result, optimum connection weights between the respective nodes constituting the neural network circuit are determined through learning based on various core design data applied to the design of a nuclear reactor core of a nuclear power plant, and axial power distributions of the nuclear reactor core are synthesized based on in-core detector signals measured by in-core detectors during operation of a nuclear reactor, thereby more accurately replicating axial power distributions of the nuclear reactor core throughout an overall period of fuel.

    摘要翻译： 提供了一种使用神经网络电路和使用其的核心监视系统（ICOMS）来合成核反应堆堆芯的轴向功率分布的方法，其中使用神经网络电路包括输入层，输出层， 和至少一个隐藏层，每个层被配置有至少一个节点，一个层的每个节点连接到其他层的节点，节点到节点连接是用连接权重进行的，所述连接权重基于学习结果而变化，最优 通过基于应用于核电站的核反应堆核心的设计的各种核心设计数据的学习来确定构成神经网络电路的各个节点之间的连接权重，并且核反应堆核心的轴向功率分布基于 核心检测器信号在核反应堆运行期间由核心检测器测量，从而更准确地复制nu的轴向功率分布 在整个燃料周期内清除反应堆堆芯。

    METHOD FOR THERMAL PERFORMANCE MONITORING OF A NUCLEAR POWER PLANT USING THE NCV METHOD
    8.
    发明公开
    METHOD FOR THERMAL PERFORMANCE MONITORING OF A NUCLEAR POWER PLANT USING THE NCV METHOD 审中-公开

    公开(公告)号：US20240127978A1

    公开(公告)日：2024-04-18

    申请号：US17887860

    申请日：2022-08-15

    申请人： Fred Donald Lang

    发明人： Fred Donald Lang

    IPC分类号： G21D3/00 ,  G21C17/108 ,  G21C17/112

    CPC分类号： G21D3/002 ,  G21C17/108 ,  G21C17/112

    摘要： This invention relates to the monitoring and diagnosing of nuclear power plants for its thermal performance using the NCV Method. Its applicability comprises any nuclear reactor such as used for research, gas-cooled and liquid metal cooled systems, fast neutron systems, and the like; all producing a useful output. Its greatest applicability lies with conventional Pressurized Water Reactor (PWR) and Boiling Water Reactor (BWR) nuclear power plants generating an electric power. Its teachings of treating fission as an inertial process, a phenomena which is self-contained following incident neutron capture, allows the determination of an absolute neutron flux. This process is best treated by Second Law principles producing a total fission exergy. This invention also applies to the design of a fusion thermal system regards the determination of its Second Law viability and absolute plasma flux.