The fifth meeting of a series discussing the irradiation behaviour of the nuclear graphite cores in the UK's Advanced Gas-Cooled Reactors.
Conference Themes
The main theme of the conference is 鈥淪cience and Engineering in Collaboration to Support Safe Operation of the Graphite Reactor Cores鈥�, and abstracts may be submitted in any relevant discipline 鈥� engineering, physics, chemistry, materials science, statistical or structural analysis, etc.
Special sessions with the following more specific topic areas for discussion are under consideration:
Microstructure: Is there a common position amongst the specialists on what really counts (to determine irradiation behaviour)?
Irradiation Creep: Is irradiation creep just an amendment upon dimensional-change behaviour?
Reactor Inspection: Can we inspect just part of a core to understand the state of the whole core with adequate confidence?
Cracking of Components: Are the consequences of cracking greater for single cracking compared with doubly-cracked bricks?
Papers need NOT, however, be confined to these specific topics, and contributions on all aspects of the nuclear graphite life cycle (in the AGR context) will be considered.
Conference Themes
The main theme of the conference is 鈥淪cience and Engineering in Collaboration to Support Safe Operation of the Graphite Reactor Cores鈥�, and abstracts may be submitted in any relevant discipline 鈥� engineering, physics, chemistry, materials science, statistical or structural analysis, etc.
Special sessions with the following more specific topic areas for discussion are under consideration:
Microstructure: Is there a common position amongst the specialists on what really counts (to determine irradiation behaviour)?
Irradiation Creep: Is irradiation creep just an amendment upon dimensional-change behaviour?
Reactor Inspection: Can we inspect just part of a core to understand the state of the whole core with adequate confidence?
Cracking of Components: Are the consequences of cracking greater for single cracking compared with doubly-cracked bricks?
Papers need NOT, however, be confined to these specific topics, and contributions on all aspects of the nuclear graphite life cycle (in the AGR context) will be considered.
