Characterisation of SCK-CEN fuel samples used for leach tests in FIRST-Nuclides
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Abstract
In the framework of the FIRST-Nuclides program, SCK•CEN will conduct leaching experiments on a PWR UOX fuel, taken from the Belgian Tihange 1 reactor, with a rod average burnup of 50 MWd/kgHM in order to determine the rapid release of some of the most critical radionuclides. Considering the influence of the irradiation parameters on the actual location of fission products at the beginning of the leaching test, the interpretation of the experimental results highly relies on a good characterization of the fuel samples. This article will deal with the characterization of the fuel rod and samples that will be used for the leach tests performed at SCK•CEN.
Details
| Original language | English |
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| Title of host publication | 1st Annual Workshop Proceedings - 7th EC - FP First-Nuclides |
| Place of Publication | Budapest, Hungary |
| Pages | ST61-ST67 |
| Publication status | Published - 10 Oct 2012 |
| Event | 1st Annual Workshop - 7th EC - FP First-Nuclides - 1st Annual Workshop Proceedings - 7th EC - FP First-Nuclides, Budapest, Hungary Duration: 9 Oct 2012 → 11 Oct 2012 |
Conference
| Conference | 1st Annual Workshop - 7th EC - FP First-Nuclides |
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| Country | Hungary |
| City | Budapest |
| Period | 2012-10-09 → 2012-10-11 |
Keywords
- First-nuclides, leaching test, high burnup, databook
ID: 384488