Irradiation and post-irradiation examination of uranium-free nitride fuel
2015 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 466, 597-605 p., 49308Article in journal (Refereed) Published
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
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
IdentifiersURN: urn:nbn:se:kth:diva-175609DOI: 10.1016/j.jnucmat.2015.08.054ISI: 000364883400072ScopusID: 2-s2.0-84941800290OAI: oai:DiVA.org:kth-175609DiVA: diva2:866367
QC 201511022015-11-022015-10-192015-12-15Bibliographically approved