This and the subsequent paper present models developed for determining fuel particle and fuel element temperatures in normal operation and transient conditions in high temperature reactor cores. Multiscale modeling concepts are used to develop the models for both pebble bed and prismatic core types. This paper, Part I, presents the development of the model for pebble bed reactors. Comparison is made with finite element simulations of an idealized “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 multibatch recycle refuelling regime. Implementation of the multiscale and multibatch fuel models in a whole-core computational fluid dynamics model is discussed together with the future intentions of the research program.
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January 2010
Research Papers
Development of Local Heat Transfer Models for Safety Assessment of High Temperature Gas-Cooled Reactor Cores—Part I: Pebble Bed Reactors
Richard Stainsby,
Richard Stainsby
AMEC Nuclear
, Knutsford, Cheshire WA16 8QZ, UK
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Matthew Worsley,
Matthew Worsley
AMEC Nuclear
, Knutsford, Cheshire WA16 8QZ, UK
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Andrew Grief,
Andrew Grief
AMEC Nuclear
, Knutsford, Cheshire WA16 8QZ, UK
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Frances Dawson,
Frances Dawson
AMEC Nuclear
, Knutsford, Cheshire WA16 8QZ, UK
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Mike Davies,
Mike Davies
AMEC Nuclear
, Knutsford, Cheshire WA16 8QZ, UK
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Paul Coddington,
Paul Coddington
AMEC Nuclear
, Knutsford, Cheshire WA16 8QZ, UK
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Jo Baker,
Jo Baker
AMEC Nuclear
, Knutsford, Cheshire WA16 8QZ, UK
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Ana Dennier
Ana Dennier
AMEC NSS
, Toronto, ON, M591X6 Canada
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Richard Stainsby
AMEC Nuclear
, Knutsford, Cheshire WA16 8QZ, UK
Matthew Worsley
AMEC Nuclear
, Knutsford, Cheshire WA16 8QZ, UK
Andrew Grief
AMEC Nuclear
, Knutsford, Cheshire WA16 8QZ, UK
Frances Dawson
AMEC Nuclear
, Knutsford, Cheshire WA16 8QZ, UK
Mike Davies
AMEC Nuclear
, Knutsford, Cheshire WA16 8QZ, UK
Paul Coddington
AMEC Nuclear
, Knutsford, Cheshire WA16 8QZ, UK
Jo Baker
AMEC Nuclear
, Knutsford, Cheshire WA16 8QZ, UK
Ana Dennier
AMEC NSS
, Toronto, ON, M591X6 CanadaJ. Eng. Gas Turbines Power. Jan 2010, 132(1): 012906 (9 pages)
Published Online: October 7, 2009
Article history
Received:
November 28, 2008
Revised:
February 12, 2009
Published:
October 7, 2009
Connected Content
A companion article has been published:
Development of Local Heat Transfer Models for the Safety Assessment of High Temperature Gas-Cooled Reactor Cores—Part II: Prismatic Modular Reactors
Citation
Stainsby, R., Worsley, M., Grief, A., Dawson, F., Davies, M., Coddington, P., Baker, J., and Dennier, A. (October 7, 2009). "Development of Local Heat Transfer Models for Safety Assessment of High Temperature Gas-Cooled Reactor Cores—Part I: Pebble Bed Reactors." ASME. J. Eng. Gas Turbines Power. January 2010; 132(1): 012906. https://doi.org/10.1115/1.3126775
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