Irradiation of thorium-bearing molten fluoride salt in graphite crucibles

P. R. Hania, D. A. Boomstra, O. Benes, A. J. de Koning, S. de Groot, R. J.M. Konings, E. Capelli, P. J. Baas, G. I.A. Lippens, More Authors

Research output: Contribution to journalArticleScientificpeer-review

Abstract

Four fluoride fuel salt samples (78LiF-22ThF4) in graphite crucibles were irradiated in the HFR Petten for a duration of 508 Full Power Days under the name SALIENT-01 (SALt Irradiation ExperimeNT). Goal of the experiment was to gain experience with the design of liquid salt experiments and the handling of the salts before and after irradiation. Specific research goals for SALIENT-01 are (i) to confirm claims of good fission product retention in the salt, (ii) to obtain size distributions for noble metal particles using Transmission Electron Microscopy and (iii) to assess possible interactions between fuel salt and fine-grained nuclear graphite, as well as possible uptake of fission products by the graphite. Here the design and irradiation history of the experiment are discussed together with plans for post-irradiation examinations. Limitations in representativeness of this experiment and capsule irradiations in general are discussed as well as follow-up actions to improve the quality of future irradiations.

Original languageEnglish
Article number111094
JournalNuclear Engineering and Design
Volume375
DOIs
Publication statusPublished - 2021

Keywords

  • Design
  • Fission product behaviour
  • Fuel
  • Molten salt
  • MTR irradiation

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