This paper presents a model developed for determining fuel particle and fuel pebble temperatures in normal operation and transient conditions based on multi-scale modelling techniques. This model is qualified by comparison with an analytical solution in a one-dimensional linear steady state test problem. Comparison is made with finite element simulations of an idealised “two-dimensional” pebble in transient conditions and with a steady state analytical solution in a spherical pebble geometry. A method is presented for determining the fuel temperatures in the individual batches of a multi-batch recycle refuelling regime. Implementation of the multi-scale and multibatch fuel models in a whole-core CFD model is discussed together with the future intentions of the research programme.
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Fourth International Topical Meeting on High Temperature Reactor Technology
September 28–October 1, 2008
Washington, DC, USA
Conference Sponsors:
- ASME
ISBN:
978-0-7918-4854-8
PROCEEDINGS PAPER
Development of Local Heat Transfer Models for Safety Assessment of Pebble Bed High Temperature Gas-Cooled Reactor Cores
Richard Stainsby,
Richard Stainsby
AMEC Nuclear, Knutsford, Cheshire, UK
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Matthew Worsley,
Matthew Worsley
AMEC Nuclear, Knutsford, Cheshire, UK
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Andrew Grief,
Andrew Grief
AMEC Nuclear, Knutsford, Cheshire, UK
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Ana Dennier,
Ana Dennier
AMEC Nuclear, Toronto, ON, Canada
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Frances Dawson,
Frances Dawson
AMEC Nuclear, Knutsford, Cheshire, UK
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Mike Davies,
Mike Davies
AMEC Nuclear, Knutsford, Cheshire, UK
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Paul Coddington,
Paul Coddington
AMEC Nuclear, Knutsford, Cheshire, UK
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Jo Baker
Jo Baker
AMEC Nuclear, Knutsford, Cheshire, UK
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Richard Stainsby
AMEC Nuclear, Knutsford, Cheshire, UK
Matthew Worsley
AMEC Nuclear, Knutsford, Cheshire, UK
Andrew Grief
AMEC Nuclear, Knutsford, Cheshire, UK
Ana Dennier
AMEC Nuclear, Toronto, ON, Canada
Frances Dawson
AMEC Nuclear, Knutsford, Cheshire, UK
Mike Davies
AMEC Nuclear, Knutsford, Cheshire, UK
Paul Coddington
AMEC Nuclear, Knutsford, Cheshire, UK
Jo Baker
AMEC Nuclear, Knutsford, Cheshire, UK
Paper No:
HTR2008-58293, pp. 129-138; 10 pages
Published Online:
July 1, 2009
Citation
Stainsby, R, Worsley, M, Grief, A, Dennier, A, Dawson, F, Davies, M, Coddington, P, & Baker, J. "Development of Local Heat Transfer Models for Safety Assessment of Pebble Bed High Temperature Gas-Cooled Reactor Cores." Proceedings of the Fourth International Topical Meeting on High Temperature Reactor Technology. Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 1. Washington, DC, USA. September 28–October 1, 2008. pp. 129-138. ASME. https://doi.org/10.1115/HTR2008-58293
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