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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
URN: urn:nbn:se:kth:diva-175609DOI: 10.1016/j.jnucmat.2015.08.054ISI: 000364883400072ScopusID: 2-s2.0-84941800290OAI: diva2:866367

QC 20151102

Available from: 2015-11-02 Created: 2015-10-19 Last updated: 2015-12-15Bibliographically approved

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Wallenius, Janne
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