Estimating fuel channel bore from fuel grab load trace data

C. Berry, D. Pattison, G. M. West, S.D.J. McArthur, A. Rudge

Research output: Chapter in Book/Report/Conference proceedingConference contribution book

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Abstract

Detailed measurements of the graphite core fuel channels are made by specialist inspection equipment during planned outages, typically every 18 months to 3 years. The bores of the graphite fuel bricks are obtained during these inspections and are used to provide important information about the health of the core. Additionally, less detailed online monitoring data is obtained much more frequently during refuelling events, called the fuel grab load trace (FGLT), which can be also used to infer the health of the graphite core. This paper describes the process of creating a model which isolates a component of the refuelling data and maps it directly to dimensional measurements of fuel channel bore. The model is created from a combination of the theoretical understanding of the physical interactions of the fuel stringer during refuelling events and several years of refuelling and inspection data to estimate suitable model parameters. Initially the model created was a coarse estimation of FGLT to fuel bore dimension but through refinements a much more accurate model has been created. An application of this model is shown through a case study of a recent outage where estimations were made on refuelling data and were compared to previously unseen inspection data.
Original languageEnglish
Title of host publicationThe 5th EDF Energy Nuclear Graphite Symposium
Place of PublicationWarrington
Number of pages8
Publication statusAccepted/In press - 8 Jan 2017
Event5th EDF Energy Generation Ltd Nuclear Graphite Conference - Southampton, United Kingdom
Duration: 10 May 201612 May 2016

Conference

Conference5th EDF Energy Generation Ltd Nuclear Graphite Conference
Country/TerritoryUnited Kingdom
CitySouthampton
Period10/05/1612/05/16

Keywords

  • fuel grab load trace
  • monitoring
  • inspection
  • graphite core
  • refuelling
  • advanced gas-cooled reactor

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