Key differences in the fabrication, irradiation and high temperature accident testing of US and German TRISO-coated particle fuel, and their implications on fuel performance

Historically, the irradiation performance of TRISO-coated gas reactor particle fuel in Germany has been superior to that in the US. German fuel generally has displayed gas release values during irradiation three orders of magnitude lower than US fuel. Thus, we have critically examined the TRISO-coat...

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Bibliographic Details
Published in:Nuclear engineering and design 2003-06, Vol.222 (2), p.281-297
Main Authors: Petti, D.A., Buongiorno, J., Maki, J.T., Hobbins, R.R., Miller, G.K.
Format: Article
Language:English
Subjects:
ACCELERATION
ACCIDENTS
Applied sciences
BURNUP
Energy
Energy. Thermal use of fuels
Exact sciences and technology
FABRICATION
FAST NEUTRONS
Fission nuclear power plants
gas cooled reactor
GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
Installations for energy generation and conversion: thermal and electrical energy
IRRADIATION
POST-IRRADIATION EXAMINATION
PROCESSING
TESTING
TRISO-Coated
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Summary:Historically, the irradiation performance of TRISO-coated gas reactor particle fuel in Germany has been superior to that in the US. German fuel generally has displayed gas release values during irradiation three orders of magnitude lower than US fuel. Thus, we have critically examined the TRISO-coated fuel fabrication processes in the US and Germany and the associated irradiation database with a goal of understanding why the German fuel behaves acceptably, why the US fuel has not faired as well, and what process/production parameters impart the reliable performance to this fuel form. The postirradiation examination results are also reviewed to identify failure mechanisms that may be the cause of the poorer US irradiation performance. This comparison will help determine the roles that particle fuel process/product attributes and irradiation conditions (burnup, fast neutron fluence, temperature, degree of acceleration) have on the behavior of the fuel during irradiation and provide a more quantitative linkage between acceptable processing parameters, as-fabricated fuel properties and subsequent in-reactor performance.
ISSN:0029-5493
1872-759X
DOI:10.1016/S0029-5493(03)00033-5