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Method for analysis of pellet-cladding interaction

一种交互作用、芯块的技术，应用在核反应的控制、核工程解决方案、计算机执行的核控制等方向

Active Publication Date: 2007-12-12
WESTINGHOUSE ELECTRIC CORP
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  • Summary
  • Abstract
  • Description
  • Claims
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Problems solved by technology

[0007] Therefore, there is room for improvement in the PCI analysis of nuclear reactors

Method used

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  • Method for analysis of pellet-cladding interaction
  • Method for analysis of pellet-cladding interaction
  • Method for analysis of pellet-cladding interaction

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[0053] For comparison, the same nuclear power plant operating period (for example, cycle), the same number of operating histories, and the same number of times within the operating period were analyzed using both methods. Specifically, in both methods approximately 2-3 run histories are each analyzed at 3-4 different times during the period. There are significant differences between the above two methods of analysis, as will now be discussed.

[0054] Then, for the traditional method, in addition to the previous steps, each of the 3-6 operating histories is analyzed between about 12-32 different normal operating maneuvers, each maneuver being analyzed for about 30-60 time steps. This is followed by the application and analysis of approximately 4-8 Case II transients starting at each normal operating state point. Each Case II transient must also be analyzed for approximately 10-150 time steps starting at the normal operating state point. For each fuel rod, the power history o...

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Abstract

A method is provided for evaluating pellet-cladding interaction (PCI) in a nuclear core having a reactor protection system and a plurality of elongated fuel rods each having fuel surrounded by cladding with a gap therebetween. The method includes: selecting a number of core parameters to be analyzed; evaluating the selected parameters at a plurality of statepoints; generating a model of an operating space of the core based, at least in part, upon the statepoints; selecting a subset or loci of statepoints from the model wherein each of the statepoints of the loci of statepoints, when subjected to a predetermined transient, falls within the operational limits of the reactor protection system; and evaluating the loci of statepoints for PCI in response to the transient. In this manner, the potential for PCI can be accurately determined without requiring every statepoint for every fuel rod in the core to be individually analyzed.

Description

technical field [0001] The present invention relates generally to the analysis of fuel failures in nuclear reactors, and more particularly to a method of analyzing pellet-cladding interaction (PCI) in a Case II event. Background technique [0002] Commercial light water nuclear reactors (LWRs) typically include a plurality of cylindrical fuel elements grouped and protected together as individual fuel assemblies. The fuel assemblies are then arranged in an organized array to form the core of a nuclear reactor. [0003] As shown in FIG. 1 , each nuclear fuel element or rod 2 includes a plurality of fuel pellets 4 (such as, without limitation, uranium dioxide) encased within a zirconium alloy cladding 6 having a first end 8 and a second end 10 . The first and second ends 8, 10 are covered by end plugs 12, 14 as shown. Typically, a compression spring 16 or other suitable restraint mechanism maintains the position of the fuel pellet 4 by biasing the pellet 4 towards the bottom...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C17/00
CPCG21C17/00G21Y2004/40G21D3/001G21Y2002/202G21C2003/047Y02E30/39G21C3/047Y02E30/30Y02E30/00G21C7/00
Inventor 查尔斯·比阿德托希欧·摩瑞塔R.·韦德·米利尔
Owner WESTINGHOUSE ELECTRIC CORP
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