An automated intelligent analysis system for analysing reactor refuelling events

Research output: Contribution to conferencePaper

Abstract

Within the UK a number of AGR stations are entering the latter stages of their original operating lives. One of the major factors for determining the operational life of an AGR station is the condition of the graphite bricks that comprise the reactor core. Routine outage inspections are now supported through the analysis of refuelling data, which provides more regular, albeit less detailed, information about the condition of the graphite core bricks. The volume of data generated and the amount of time and expertise required to analyse the data is a significant issue. This paper describes the development and deployment of an automated intelligent analysis system for fuel grab load trace (FGLT) data. This is an example of a system that was developed to leverage existing plant equipment to provide additional benefit to the station operators, through the application of intelligent analysis techniques. This paper describes the design, implementation and testing of the British Energy Trace Analysis (BETA) system, that automatically assesses event data gathered during routine refuelling operations to provide information relating to the condition of the graphite core bricks in the AGR reactor. Issues such as the reuse of existing data sources from legacy systems to support the monitoring process are discussed, which is timely considering that the AGR stations are entering the phase of their operation lives where lifetime extension is being considered.

Conference

ConferenceInternational Conference on Control and Instrumentation in Nuclear Installations
CountryUnited Kingdom
CityManchester
Period11/09/0713/09/07

Fingerprint

Reactor refueling
Brick
Graphite
Trace analysis
Legacy systems
Reactor cores
Process monitoring
Outages
Inspection
Testing

Keywords

  • reactor refuelling
  • design
  • automated intelligent analysis
  • equipment

Cite this

West, G., Mcarthur, S., Mcdonald, J., & Towle, D. (2007). An automated intelligent analysis system for analysing reactor refuelling events. Paper presented at International Conference on Control and Instrumentation in Nuclear Installations, Manchester, United Kingdom.
West, Graeme ; Mcarthur, Stephen ; Mcdonald, James ; Towle, Dave. / An automated intelligent analysis system for analysing reactor refuelling events. Paper presented at International Conference on Control and Instrumentation in Nuclear Installations, Manchester, United Kingdom.
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note = "International Conference on Control and Instrumentation in Nuclear Installations ; Conference date: 11-09-2007 Through 13-09-2007",

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West, G, Mcarthur, S, Mcdonald, J & Towle, D 2007, 'An automated intelligent analysis system for analysing reactor refuelling events' Paper presented at International Conference on Control and Instrumentation in Nuclear Installations, Manchester, United Kingdom, 11/09/07 - 13/09/07, .

An automated intelligent analysis system for analysing reactor refuelling events. / West, Graeme; Mcarthur, Stephen; Mcdonald, James; Towle, Dave.

2007. Paper presented at International Conference on Control and Instrumentation in Nuclear Installations, Manchester, United Kingdom.

Research output: Contribution to conferencePaper

TY - CONF

T1 - An automated intelligent analysis system for analysing reactor refuelling events

AU - West, Graeme

AU - Mcarthur, Stephen

AU - Mcdonald, James

AU - Towle, Dave

PY - 2007/9/11

Y1 - 2007/9/11

N2 - Within the UK a number of AGR stations are entering the latter stages of their original operating lives. One of the major factors for determining the operational life of an AGR station is the condition of the graphite bricks that comprise the reactor core. Routine outage inspections are now supported through the analysis of refuelling data, which provides more regular, albeit less detailed, information about the condition of the graphite core bricks. The volume of data generated and the amount of time and expertise required to analyse the data is a significant issue. This paper describes the development and deployment of an automated intelligent analysis system for fuel grab load trace (FGLT) data. This is an example of a system that was developed to leverage existing plant equipment to provide additional benefit to the station operators, through the application of intelligent analysis techniques. This paper describes the design, implementation and testing of the British Energy Trace Analysis (BETA) system, that automatically assesses event data gathered during routine refuelling operations to provide information relating to the condition of the graphite core bricks in the AGR reactor. Issues such as the reuse of existing data sources from legacy systems to support the monitoring process are discussed, which is timely considering that the AGR stations are entering the phase of their operation lives where lifetime extension is being considered.

AB - Within the UK a number of AGR stations are entering the latter stages of their original operating lives. One of the major factors for determining the operational life of an AGR station is the condition of the graphite bricks that comprise the reactor core. Routine outage inspections are now supported through the analysis of refuelling data, which provides more regular, albeit less detailed, information about the condition of the graphite core bricks. The volume of data generated and the amount of time and expertise required to analyse the data is a significant issue. This paper describes the development and deployment of an automated intelligent analysis system for fuel grab load trace (FGLT) data. This is an example of a system that was developed to leverage existing plant equipment to provide additional benefit to the station operators, through the application of intelligent analysis techniques. This paper describes the design, implementation and testing of the British Energy Trace Analysis (BETA) system, that automatically assesses event data gathered during routine refuelling operations to provide information relating to the condition of the graphite core bricks in the AGR reactor. Issues such as the reuse of existing data sources from legacy systems to support the monitoring process are discussed, which is timely considering that the AGR stations are entering the phase of their operation lives where lifetime extension is being considered.

KW - reactor refuelling

KW - design

KW - automated intelligent analysis

KW - equipment

M3 - Paper

ER -

West G, Mcarthur S, Mcdonald J, Towle D. An automated intelligent analysis system for analysing reactor refuelling events. 2007. Paper presented at International Conference on Control and Instrumentation in Nuclear Installations, Manchester, United Kingdom.