Postirradiation examination from separate effects irradiation testing of uranium nitride kernels and coated particles

Harp, Jason M.; Morris, Robert N.; Petrie, Christian M.; Burns, Joseph R.; Terrani, Kurt A.

doi:10.1016/j.jnucmat.2020.152696

Postirradiation examination from separate effects irradiation testing of uranium nitride kernels and coated particles

Journal Article · Thu Nov 26 00:00:00 EST 2020 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2020.152696· OSTI ID:1735424

^[1]; ^[1]; ^[1]; ^[1]; ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

An overview of postirradiation examination results for uranium nitride kernels and uranium nitride coated particles irradiated in the High Flux Isotope Reactor are presented. This is the first postirradiation examination of the MiniFuel irradiation vehicle that was recently developed to rapidly accumulate burnup during separate effects irradiation testing. In general, the burnup and fuel temperatures measured postirradiation were consistent with the design calculations. The burnup measured by mass spectrometry ranged from 5.9 to 10 MWd/kgU and was achieved after only 68 effective full-power days of irradiation. The dilatometric evaluation of passive silicon carbide thermometry indicated that the fuel was irradiated at temperatures ranging from 410 to 460 °C. Because the irradiation temperatures and burnup were low, the UN kernels showed minimal fission gas release that was within the range of the expected recoil (athermal) release. While it is possible to measure fuel swelling using x-ray computed tomography, the observed swelling was too small to quantify in this case. Extensive microstructural characterization of the irradiated fuel was performed in this study, and no significant irradiation induced changes were observed.

View Accepted Manuscript (DOE)

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1735424

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: N/A Vol. 544; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (19)

Fission product release from nuclear fuel by recoil and knockout Lewis, B. J. Journal of Nuclear Materials, Vol. 148, Issue 1 https://doi.org/10.1016/0022-3115(87)90515-0	journal	March 1987
Uranium nitride fuel swelling correlation Ross, Steven B.; El-Genk, Mohamed S.; Matthews, R. Bruce Journal of Nuclear Materials, Vol. 170, Issue 2 https://doi.org/10.1016/0022-3115(90)90409-G	journal	February 1990
Fuel fabrication processes, design and experimental conditions for the joint US-Swiss mixed carbide test in FFTF (AC-3 test) Stratton, R. W.; Ledergerber, G.; Ingold, F. Journal of Nuclear Materials, Vol. 204 https://doi.org/10.1016/0022-3115(93)90197-7	journal	September 1993
Nitride Fuel Arai, Y. Comprehensive Nuclear Materials https://doi.org/10.1016/B978-0-08-056033-5.00050-1	book	February 2012
Development of a fast and efficient analytical technique for the isotopic analysis of fission and actinide elements in environmental matrices Roach, Benjamin D.; Fenske, Emilie K.; Ilgner, Ralph H. Journal of Chromatography A, Vol. 1587 https://doi.org/10.1016/j.chroma.2018.12.029	journal	February 2019
Fission gas release and swelling in uranium–plutonium mixed nitride fuels Tanaka, Kosuke; Maeda, Koji; Katsuyama, Kozo Journal of Nuclear Materials, Vol. 327, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2004.01.002	journal	May 2004
An approach to fuel development and qualification Crawford, Douglas C.; Porter, Douglas L.; Hayes, Steven L. Journal of Nuclear Materials, Vol. 371, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2007.05.029	journal	September 2007
Fission product release and survivability of UN-kernel LWR TRISO fuel Besmann, T. M.; Ferber, M. K.; Lin, H. -T. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.10.034	journal	May 2014
Investigation of sol-gel feedstock additions and process variables on the density and microstructure of UN microspheres McMurray, J. W.; Hunt, R. D.; Reif, T. J. Journal of Nuclear Materials, Vol. 520 https://doi.org/10.1016/j.jnucmat.2019.04.003	journal	July 2019
Separate effects irradiation testing of miniature fuel specimens Petrie, Christian M.; Burns, Joseph R.; Raftery, Alicia M. Journal of Nuclear Materials, Vol. 526 https://doi.org/10.1016/j.jnucmat.2019.151783	journal	December 2019
Uranium nitride tristructural-isotropic fuel particle Terrani, Kurt A.; Jolly, Brian C.; Harp, Jason M. Journal of Nuclear Materials, Vol. 531 https://doi.org/10.1016/j.jnucmat.2020.152034	journal	April 2020
Accelerating nuclear fuel development and qualification: Modeling and simulation integrated with separate-effects testing Terrani, Kurt A.; Capps, Nathan A.; Kerr, Matthew J. Journal of Nuclear Materials, Vol. 539 https://doi.org/10.1016/j.jnucmat.2020.152267	journal	October 2020
Evaluation of the continuous dilatometer method of silicon carbide thermometry for passive irradiation temperature determination Field, Kevin G.; McDuffee, Joel L.; Geringer, Josina W. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 445 https://doi.org/10.1016/j.nimb.2019.02.022	journal	April 2019
First elevated-temperature performance testing of coated particle fuel compacts from the AGR-1 irradiation experiment Baldwin, Charles A.; Hunn, John D.; Morris, Robert N. Nuclear Engineering and Design, Vol. 271 https://doi.org/10.1016/j.nucengdes.2013.11.021	journal	May 2014
An analysis of nuclear fuel burnup in the AGR-1 TRISO fuel experiment using gamma spectrometry, mass spectrometry, and computational simulation techniques Harp, Jason M.; Demkowicz, Paul A.; Winston, Philip L. Nuclear Engineering and Design, Vol. 278 https://doi.org/10.1016/j.nucengdes.2014.07.041	journal	October 2014
Irradiation performance of AGR-1 high temperature reactor fuel Demkowicz, Paul A.; Hunn, John D.; Ploger, Scott A. Nuclear Engineering and Design, Vol. 306 https://doi.org/10.1016/j.nucengdes.2015.09.011	journal	September 2016
Performance of AGR-1 high-temperature reactor fuel during post-irradiation heating tests Morris, Robert N.; Baldwin, Charles A.; Demkowicz, Paul A. Nuclear Engineering and Design, Vol. 306 https://doi.org/10.1016/j.nucengdes.2016.04.031	journal	September 2016
Initial results from safety testing of US AGR-2 irradiation test fuel Morris, Robert N.; Hunn, John D.; Baldwin, Charles A. Nuclear Engineering and Design, Vol. 329 https://doi.org/10.1016/j.nucengdes.2017.08.006	journal	April 2018
Initial examination of fuel compacts and TRISO particles from the US AGR-2 irradiation test Hunn, John D.; Baldwin, Charles A.; Montgomery, Fred C. Nuclear Engineering and Design, Vol. 329 https://doi.org/10.1016/j.nucengdes.2017.09.017	journal	April 2018

Similar Records

Summary of the Postirradiation Examination of the First Samples from a MiniFuel Irradiation

Technical Report · Fri Jun 12 00:00:00 EDT 2020 · OSTI ID:1731057

Fuel Performance Experience, Analysis and Modeling: Deformations, Fission Gas Release and Pellet-Clad Interaction

Conference · Sun Jul 01 00:00:00 EDT 2007 · OSTI ID:21229274

ROADRUNNER MiniFuel Experiment: Irradiation Target Design and Sample Characterization

Technical Report · Sun Sep 01 00:00:00 EDT 2024 · OSTI ID:2441067

Related Subjects

36 MATERIALS SCIENCE

Postirradiation examination from separate effects irradiation testing of uranium nitride kernels and coated particles

Citation Formats

References (19)

Similar Records

Related Subjects