For direct cycle gas cooled high temperature reactor designs, operating conditions may be limited as a result of excessive maintenance dose rates caused by the Ag-110m source term on the turbine. It is therefore important to accurately predict silver release from fuel during reactor operation. Traditionally diffusion models were used to derive transport parameters from limited irradiation testing of fuel materials and components. Best estimates for all applicable German fuel irradiation tests with defendable uncertainty ranges were never derived. However, diffusion theory and current parameters cannot account for all irradiation and heat-up test results, and for some tests, it appears unacceptably conservative. Other transport mechanisms have been suggested, and alternative calculation models are being considered. In this paper the applicable German irradiation test results are evaluated with a classic diffusion model as well as an alternative model called the Molecular Vapour transport Release (MVR) model. New transport models and parameters for silver in fuel materials are suggested and compared.
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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
Modelling Silver: Evaluation of German Experience
Hanno van der Merwe,
Hanno van der Merwe
Pebble Bed Modular Reactor (Pty.) Ltd., Centurion, Gauteng, South Africa
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Dirk Olivier
Dirk Olivier
Independent Nuclear Consultants, Grahamstown, South Africa
Search for other works by this author on:
Hanno van der Merwe
Pebble Bed Modular Reactor (Pty.) Ltd., Centurion, Gauteng, South Africa
Dirk Olivier
Independent Nuclear Consultants, Grahamstown, South Africa
Paper No:
HTR2008-58105, pp. 439-448; 10 pages
Published Online:
July 1, 2009
Citation
van der Merwe, H, & Olivier, D. "Modelling Silver: Evaluation of German Experience." 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. 439-448. ASME. https://doi.org/10.1115/HTR2008-58105
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