公开(公告)号：US07366273B2

公开(公告)日：2008-04-29

申请号：US11320919

申请日：2005-12-30

申请人： William Earl Russell, II ,  Russell Morgan Fawcett ,  William Charles Cline ,  David Joseph Kropaczek ,  Glen A. Watford ,  Lukas Trosman ,  Steven Barry Sutton ,  Christian Carlos Oyarzun

发明人： William Earl Russell, II ,  Russell Morgan Fawcett ,  William Charles Cline ,  David Joseph Kropaczek ,  Glen A. Watford ,  Lukas Trosman ,  Steven Barry Sutton ,  Christian Carlos Oyarzun

IPC分类号： G21C7/36

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。

公开(公告)号：US5174946A

公开(公告)日：1992-12-29

申请号：US644349

申请日：1991-01-22

申请人： Glen A. Watford ,  Kiran Kumar

发明人： Glen A. Watford ,  Kiran Kumar

IPC分类号： G21C17/00 ,  G21C17/10 ,  G21C17/108 ,  G21D3/00 ,  G21D3/08

CPC分类号： G21D3/001 ,  G21C17/108 ,  G21D3/08 ,  Y02E30/40

摘要： To detect core-wide and regional neutron flux oxcillations in a nuclear reactor core induced by thermal-hydraulic instabilities, local power range monitoring (LPRM) strings radially distributed throughout the core and having plural vertically spaced neutron flux detectors are locally assigned to individual oscillation power range monitoring (OPRM) cells radially distributed throughout the core. Groups of OPRM cells are assigned to different OPRM channels based on their geographical positions. Detector signals of the LPRM strings assigned to each OPRM cell are processed pursuant to a unique trip algorithm to detect neutron flux oscillations, and, upon meeting prescribed amplitude and frequency criteria, the assigned OPRM channel is tripped. Suppression of a thermal hydraulic instability is initiated when at least two OPRM channels assigned to geographically adjacent OPRM cells are tripped.

公开(公告)号：US5141710A

公开(公告)日：1992-08-25

申请号：US720131

申请日：1991-06-24

申请人： Richard C. Stirn ,  Glen A. Watford

发明人： Richard C. Stirn ,  Glen A. Watford

IPC分类号： G21C7/00 ,  G21C7/26 ,  G21C7/32 ,  G21C17/00 ,  G21D3/00 ,  G21D3/08 ,  G21D3/16

CPC分类号： G21C7/32 ,  G21D3/16 ,  Y02E30/31 ,  Y02E30/39

摘要： To stabilize boiling water reactors against neutron flux oscillations caused by thermal-hydraulic instabilities, random core-wide reactivity perturbations are induced in the reactor either to suppress the onset of asymmetric (regional) mode oscillations or, in response to the detection of asymmetric mode oscillations, to stabilize the reactor in a symmetric (core-wide) oscillation mode. The reactivity perturbations are produced by effecting random changes in dome pressure, core flow or coolant enthalpy.