Determination of operating limit minimum critical power ratio
AssigneeGlobal Nuclear Fuel - Americas, LLC
InventorsFrancis Thomas Bolger, Jens Georg Munthe Andersen, Charles Lee Heck, James Courtney Shaug
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AssigneeGlobal Nuclear Fuel - Americas, LLC
InventorsFrancis Thomas Bolger, Jens Georg Munthe Andersen, Charles Lee Heck, James Courtney Shaug
Estimating the term…
A method and system for thermal-dynamic modeling and performance evaluation of a nuclear Boiling Water Reactor (BWR) core design is presented. A data processing system is used to execute specific program routines that simultaneously simulate the thermal operating characteristics of fuel rods within the reactor during a transient operational condition. The method employs a multi-dimensional approach for the simulation of postulated operational events or an anticipated operational occurrence (AOO) which produces a transient condition in the reactor—such as might be caused by single operator error or equipment malfunction. Based on a generic transient bias and uncertainty in the change in critical power ratio (ΔCPR/ICPR), histograms of fuel rod critical power ratio (CPR) are generated. Ultimately, the operating limit minimum critical power ratio (OLMCPR) of the reactor is evaluated from a histogram of probability calculations representing the number of fuel rods subject to a boiling transition (NRSBT) during the transient condition. The histogram may be readily displayed by the data processing system and used to statistically demonstrate an OLMCPR compliance of the reactor core design with USNRC regulations.
A method for determining an operating margin for a nuclear fuel core of a Boiling Water Reactor (BWR), wherein fuel design or core configuration are contingent upon an operating margin for the reactor, said operating margin being determined by a process for evaluating an operating limit minimum critical power ratio (OLMCPR) comprising:
A method for determining an operating margin for a nuclear fuel core of a Boiling Water Reactor (BWR), wherein fuel rod design or core configuration are contingent upon an operating margin for the reactor, said operating margin being determined by a process for evaluating an operating limit minimum critical power ratio (OLMCPR), said method comprising:
For use in controlling a Boiling Water Reactor (BWR) having a nuclear fueled core characterized by an operating limit minimum critical power ratio (OLMCPR) value, a method for determining said OLMCPR value comprising:
Dependencies are inferred from the claim text.