Advanced gas-cooled reactor fuel channel bore estimation model
Young, Andrew and West, Graeme (2019) Advanced gas-cooled reactor fuel channel bore estimation model. In: 2019 Innovation Showcase: Nuclear Asset Management and Industrial Informatics, 2019-05-09 - 2019-05-10.
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Abstract
* The main life-limiting factor of an Advanced Gas-Cooled Reactors (AGRs) is the graphite core, as it cannot be repaired or replaced. * Installation of new monitoring equipment is difficult and expensive, therefore it is important to obtain the maximum amount of information from existing equipment. * Using the current bore estimation model, for most of the datasets tested, it is possible to convert low detailed monitoring data to produce results that closely match the higher detailed inspection data. refuelling events.
ORCID iDs
Young, Andrew
ORCID: https://orcid.org/0000-0001-6338-6631 and West, Graeme ORCID: https://orcid.org/0000-0003-0884-6070;
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Item type: Conference or Workshop Item(Poster) ID code: 68261 Dates: DateEvent10 May 2019PublishedKeywords: bore estimation, condition monitoring, data analytics, machine Learning, graphite, asset management, Electrical Engineering. Electronics Nuclear Engineering, Nuclear Energy and Engineering, Electrical and Electronic Engineering Subjects: Technology > Electrical engineering. Electronics Nuclear engineering Department: Faculty of Engineering > Electronic and Electrical Engineering
Strategic Research Themes > EnergyDepositing user: Pure Administrator Date deposited: 06 Jun 2019 10:22 Last modified: 18 Jan 2023 13:28 URI: https://strathprints.strath.ac.uk/id/eprint/68261
CORE (COnnecting REpositories)
CORE (COnnecting REpositories)