公开(公告)号：US20180226160A1

公开(公告)日：2018-08-09

申请号：US15888622

申请日：2018-02-05

申请人： Kabushiki Kaisha Toshiba ,  Toshiba Energy Systems & Solutions Corporation

发明人： Satoshi WADA ,  Hiroshi Matsumiya ,  Tsukasa Sugita ,  Rei Kimura ,  Rie Aizawa ,  Noriyuki Yoshida

IPC分类号： G21C7/04 ,  G21C3/07 ,  G21C21/00 ,  G21C3/30 ,  G21C3/58

CPC分类号： G21C7/04 ,  G21C3/07 ,  G21C3/30 ,  G21C3/32 ,  G21C3/58 ,  G21C21/00 ,  G21D3/001 ,  G21D3/002 ,  Y02E30/38 ,  Y02E30/39

摘要： According to an embodiment, a design method for a light-water reactor fuel assembly comprises: accumulating a determined fuel data, showing that each of a combination of p·n/N and e is feasible as the core or not, wherein N is a number of the fuel rods in the fuel assembly, n is a number of the fuel rods containing the burnable poison, p is a ratio wt % of the burnable poison in the fuel, and e is an enrichment wt % of the uranium 235 contained in the fuel assembly; formulating a criterion formula which determines whether a combination of p·n/N and e is feasible as a core or not and is formulated based on the determined fuel data; and determining whether a temporarily set composition of the fuel assembly is approved as a core or not based on the criterion formula.

公开(公告)号：US20160321383A1

公开(公告)日：2016-11-03

申请号：US15209300

申请日：2016-07-13

申请人： TerraPower, LLC

发明人： Jesse R. Cheatham, III ,  Robert C. Petroski ,  Nicholas W. Touran ,  Charles Whitmer

IPC分类号： G06F17/50 ,  G21D3/00 ,  G06F17/11

CPC分类号： G06F17/5009 ,  G06F17/11 ,  G06F2217/16 ,  G21D3/001 ,  G21D3/002 ,  G21D3/005 ,  Y02E30/40

摘要： Illustrative embodiments provide for the operation and simulation of the operation of fission reactors, including the movement of materials within reactors. Illustrative embodiments and aspects include, without limitation, nuclear fission reactors and reactor modules, including modular nuclear fission reactors and reactor modules, nuclear fission deflagration wave reactors and reactor modules, modular nuclear fission deflagration wave reactors and modules, methods of operating nuclear reactors and modules including the aforementioned, methods of simulating operating nuclear reactors and modules including the aforementioned, and the like.

摘要翻译： 示例性实施例提供了裂变反应堆的操作的操作和模拟，包括反应器内材料的移动。 说明性的实施方案和方面包括但不限于核裂变反应堆和反应堆模块，包括模块式核裂变反应堆和反应堆模块，核裂变爆燃波反应堆和反应堆模块，模块式核裂变爆燃波反应堆和模块，运行核反应堆和模块的方法 包括前述的模拟运行的核反应堆的方法和包括上述的模块等。

公开(公告)号：US20160260506A1

公开(公告)日：2016-09-08

申请号：US15029140

申请日：2013-10-21

申请人： HITACHI, LTD.

发明人： Takeshi MITSUYASU ,  Motoo AOYAMA

IPC分类号： G21C5/18 ,  G21C1/08

CPC分类号： G21C5/18 ,  G21C1/084 ,  G21C5/00 ,  G21D3/001 ,  G21D3/002 ,  Y02E30/40

摘要： The initial-core economical efficiency is improved by loading the medium enriched fuel in the peripheral or lacing it adjacent to the low enriched fuel and the highly enriched fuel. According to the present invention, in an initial core of a Boiling Water Reactor loaded with at least three types of fuel including highly enriched fuel with a fission-material content of 3.0 wt % or more, medium enriched fuel with a fission-material content of a range from 1.5 wt % or more to less than 3.0 wt %, and low enriched fuel with a fission-material content of less than 1.5 wt %, when a region of an outermost peripheral of a core occupied by the fuel having no face adjoining another fuel in a horizontal direction is defined as an outermost peripheral region, a region outside a line at 80% of a radius of a circumcircle of the core and except for the outermost peripheral region is defined as a peripheral region and the remainder is defined as an inner region, 50% or more of the fuel loaded in the peripheral region is the medium enriched fuel.

摘要翻译： 通过将富含介质的燃料装载在周边或将其附加到低浓度燃料和高浓缩燃料上来提高初始核心经济效率。 根据本发明，在装有至少三种类型燃料的沸水反应堆的初始核心中，包括裂变材料含量为3.0wt％或更高的富含高浓度燃料，具有裂变材料含量的富集燃料 在1.5重量％以上且小于3.0重量％的范围内，当燃料所占据的核的最外周的区域没有面临相邻时，裂解材料含量小于1.5重量％的低浓度燃料 将水平方向上的另一种燃料定义为最外周区域，将芯的外接圆的半径的80％的直线以外的区域除外最外周区域作为周边区域，将余数定义为 内部区域，装载在周边区域中的燃料的50％以上是富集燃料的燃料。

公开(公告)号：US20130166223A1

公开(公告)日：2013-06-27

申请号：US13336229

申请日：2011-12-23

申请人： Brian S. Triplett

发明人： Brian S. Triplett

IPC分类号： G06F19/00

CPC分类号： G21C17/108 ,  G21C17/104 ,  G21D3/001 ,  G21D3/002 ,  Y02E30/40

摘要： Methods implemented by at least one electronic processor for generating pointwise fast neutron spectra may include receiving composition data; receiving source data or calculating the source data; receiving nuclear data; and calculating the pointwise fast neutron spectrum based on numerical integration using the composition, source, and nuclear data. Systems for generating pointwise fast neutron spectra may include a bus; at least one electronic processor connected to the bus; an input device connected to the bus; and a communication link connected to the bus. The at least one electronic processor may be configured to receive composition data from the input device via the bus, to receive source data from the input device via the bus or to calculate the source data, to receive nuclear data from the communication link via the bus, and to calculate the pointwise fast neutron spectrum based on numerical integration using the composition, source, and nuclear data.

摘要翻译： 由至少一个电子处理器实现的用于产生点快中子谱的方法可以包括接收合成数据; 接收源数据或计算源数据; 接收核数据; 并使用组合，源和核数据计算基于数值积分的点快中子谱。 用于生成点快中子谱的系统可以包括总线; 连接到总线的至少一个电子处理器; 连接到总线的输入设备; 以及连接到总线的通信链路。 所述至少一个电子处理器可以被配置为经由总线从输入设备接收合成数据，以经由总线从输入设备接收源数据或者计算源数据，以经由总线从通信链路接收核数据 ，并使用组合，源和核数据基于数值积分计算点快中子谱。

公开(公告)号：US20090168946A1

公开(公告)日：2009-07-02

申请号：US11968196

申请日：2008-01-02

申请人： YANG-KAI CHIU

发明人： YANG-KAI CHIU

IPC分类号： G21C17/108

CPC分类号： G21C7/00 ,  G21C17/108 ,  G21D3/001 ,  G21D3/002 ,  G21D3/005 ,  Y02E30/31 ,  Y02E30/39

摘要： An analytical method for the initial flux and transient hot water flow parameters for a boiling water reactor with single fuel bundle. Firstly, the method is to calculate intial flux and transient hot water flow parameter based on single fuel bundle. Then, it uses supplier provided CPR (Critical Power Ratio) correlation to calculate transient CPR and calculate the whole reactor core for hot water parameters as boundary condition. Iteration is used to figure out DCPR (Delta Critical Power Ratio). The obtained limit transient is selected as the maximum from DCPR. The maximum transient DCPR combines Safety Limit Minimum Critical Power Ratio (SLMCPR) and safety margin to figure out the OLMCPR (Operating Limit Minimum Critical Power Ratio). Both the plant layout and operational thermal limit are based on OLMCPR to assure the safety of reactor core.

摘要翻译： 具有单燃料束的沸水反应堆的初始通量和瞬时热水流动参数的分析方法。 首先，该方法是基于单燃料束计算初始通量和瞬时热水流量参数。 然后，使用供应商提供的CPR（临界功率比）相关性来计算临时CPR，并计算热水参数的整个反应堆核心作为边界条件。 迭代用于计算DCPR（Delta临界功率比）。 所获得的极限瞬变被选为DCPR的最大值。 最大瞬态DCPR组合了安全极限最小临界功率比（SLMCPR）和安全裕度，以计算出OLMCPR（工作极限最小临界功率比）。 工厂布局和运行热限都基于OLMCPR，以确保反应堆堆芯的安全。

公开(公告)号：US20040191734A1

公开(公告)日：2004-09-30

申请号：US10401601

申请日：2003-03-31

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： G09B009/00

CPC分类号： G21D3/001 ,  G06F17/5009 ,  G06F2217/04 ,  G06F2217/80 ,  G21C19/205 ,  G21D3/002 ,  Y02E30/40

摘要： In the method, a set of limits applicable to a core may be defined, and a test fresh fuel 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 fresh fuel loading pattern, creating one or more derivative fresh fuel loading pattern design(s) for simulation and eventual perfection as an acceptable fresh fuel 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新鲜燃料加载模式设计。 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新鲜燃料装载模式，创建一个或多个用于模拟和最终完善的衍生新鲜燃料装载模式设计，作为核心的可接受的新鲜燃料加载模式设计。