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Irradiation and post-irradiation examination of uranium-free nitride fuel
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2015 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 466, 597-605 p., 49308Article in journal (Refereed) Published
Abstract [en]

Two identical Phénix-type 15-15Ti steel pinlets each containing a 70 mm Pu<inf>0.3</inf>Zr<inf>0.7</inf>N fuel stack in a 1-bar helium atmosphere have been irradiated in the HFR Petten at medium high linear power (46-47 kW/m at BOL) and an average cladding temperature of 505 °C. The pins were irradiated to a plutonium burn-up of 9.7% (88 MWd/kg<inf>HM</inf>) in 170 full power days. Both pins remained fully intact. Post-irradiation examination performed at NRG and PSI showed that the overall swelling rate of the fuel was 0.92 vol-%/%FIHMA. Fission gas release was 5-6%, while helium release was larger than 50%. No fuel restructuring was observed, and only mild cracking. EPMA measurements show a burn-up increase toward the pellet edge of up to 4 times. All investigated fission products except to some extent the noble metals were found to be evenly distributed over the matrix, indicating good solubility. Local formation of a secondary phase with high Pu content and hardly any Zr was observed. A general conclusion of this investigation is that ZrN is a suitable inert matrix for burning plutonium at high destruction rates.

Place, publisher, year, edition, pages
2015. Vol. 466, 597-605 p., 49308
Keyword [en]
Fission products, Fuels, Helium, Plutonium, Zirconium, Cladding temperatures, Destruction rates, Fission gas release, Helium atmosphere, Helium release, Post irradiation examinations, Secondary phase, Swelling rates, Irradiation
National Category
Chemical Sciences
Identifiers
URN: urn:nbn:se:kth:diva-175609DOI: 10.1016/j.jnucmat.2015.08.054ISI: 000364883400072Scopus ID: 2-s2.0-84941800290OAI: oai:DiVA.org:kth-175609DiVA: diva2:866367
Note

QC 20151102

Available from: 2015-11-02 Created: 2015-10-19 Last updated: 2017-12-01Bibliographically approved

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Wallenius, Janne

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