The evaluation of fission gas release from spherical fuel during irradiation testing is critical to understand expected fuel performance under real reactor conditions. Online measurements of Krypton and Xenon fission products explain coated particle performance and contributions from graphitic matrix materials used in fuel manufacture and irradiation rig materials. Methods that are being developed to accurately evaluate fission gas release are described here together with examples of evaluations performed on irradiation tests HFR-K5, -K6 and EU1bis.
A Method to Evaluate Fission Gas Release During Irradiation Testing of Spherical Fuel
van der Merwe, H, & Venter, J. "A Method to Evaluate Fission Gas Release During Irradiation Testing of Spherical Fuel." 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. 329-338. ASME. https://doi.org/10.1115/HTR2008-58184
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