Detailed measurements of local thickness changes for U-7Mo dispersion fuel plates with Al-3.5Si matrix after irradiation at different powers in the RERTR-9B experiment

Keiser, Jr., Dennis D.; Williams, Walter; Robinson, Adam; Wachs, Dan; Clark, Curtis; Crawford, Doug

doi:10.1016/j.jnucmat.2017.07.047

Title: Detailed measurements of local thickness changes for U-7Mo dispersion fuel plates with Al-3.5Si matrix after irradiation at different powers in the RERTR-9B experiment

Journal Article · Thu Jul 27 00:00:00 EDT 2017 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2017.07.047· OSTI ID:1631701

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Idaho National Lab. (INL), Idaho Falls, ID (United States)

The Materials Management and Minimization program is developing fuel designs to replace highly enriched fuel with fuels of low enrichment. Swelling is an important irradiation behavior that needs to be well understood. Data from high resolution thickness measurements performed on U-7Mo dispersion fuel plates with Al-Si alloy matrices that were irradiated at high power is sparse. This paper reports the results of detailed thickness measurements performed on two dispersion fuel plates that were irradiated at relatively high power to high fission densities in the Advanced Test Reactor in the same RERTR-9B experiment. Both plates were irradiated to similar fission densities, but one was irradiated at a higher power than the other. The goal of this work is to identify any differences in the swelling behavior when fuel plates are irradiated at different powers to the same fission densities. Based on the results of detailed thickness measurments, more swelling occurs when a U-7Mo dispersion fuel with Al-3.5Si matrix is irradiated to a high fission density at high power compared to one irradiated at a lower power to high fission density.

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Research Organization:: Idaho National Lab. (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1631701

Alternate ID(s):: OSTI ID: 1549634

Report Number(s):: INL/JOU-17-42001-Rev000; TRN: US2201007

Journal Information:: Journal of Nuclear Materials, Vol. 494, Issue C; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 6 works

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References (10)

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Swelling of U(Mo)–Al(Si) dispersion fuel under irradiation – Non-destructive analyses of the LEONIDAS E-FUTURE plates Van den Berghe, S.; Parthoens, Y.; Charollais, F. Journal of Nuclear Materials, Vol. 430, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.06.045	journal	November 2012
Swelling of U(Mo) dispersion fuel under irradiation – Non-destructive analyses of the SELENIUM plates Van den Berghe, S.; Parthoens, Y.; Cornelis, G. Journal of Nuclear Materials, Vol. 442, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.08.020	journal	November 2013
Swelling of U-7Mo/Al-Si dispersion fuel plates under irradiation – Non-destructive analysis of the AFIP-1 fuel plates Wachs, D. M.; Robinson, A. B.; Rice, F. J. Journal of Nuclear Materials, Vol. 476 https://doi.org/10.1016/j.jnucmat.2016.04.048	journal	August 2016
Effect of fission rate on the microstructure of coated UMo dispersion fuel Leenaers, A.; Parthoens, Y.; Cornelis, G. Journal of Nuclear Materials, Vol. 494 https://doi.org/10.1016/j.jnucmat.2017.06.036	journal	October 2017
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Fuel swelling and interaction layer formation in the SELENIUM Si and ZrN coated U(Mo) dispersion fuel plates irradiated at high power in BR2 Leenaers, A.; Van den Berghe, S.; Koonen, E. Journal of Nuclear Materials, Vol. 458 https://doi.org/10.1016/j.jnucmat.2014.12.073	journal	March 2015

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Title: Detailed measurements of local thickness changes for U-7Mo dispersion fuel plates with Al-3.5Si matrix after irradiation at different powers in the RERTR-9B experiment

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