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

Abstract

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.

Authors:

^[1];

^[1]

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

Publication Date:: Thu Jul 27 00:00:00 EDT 2017

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

Sponsoring Org.:: USDOE National Nuclear Security Administration (NNSA)

OSTI Identifier:: 1631701

Alternate Identifier(s):: OSTI ID: 1549634

Report Number(s):: INL/JOU-17-42001-Rev000
Journal ID: ISSN 0022-3115; TRN: US2201007

Grant/Contract Number:: AC07-05ID14517

Resource Type:: Accepted Manuscript

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Volume: 494; Journal Issue: C; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Low-enriched uranium fuel; uranium molybdenum alloy; dispersion fuel; nuclear fuel; swelling; plate fuel; research reactors

Citation Formats


                    Keiser, Jr., Dennis D., Williams, Walter, Robinson, Adam, Wachs, Dan, Clark, Curtis, and Crawford, Doug. 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.  United States: N. p., 2017. 
Web.  doi:10.1016/j.jnucmat.2017.07.047.

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                    Keiser, Jr., Dennis D., Williams, Walter, Robinson, Adam, Wachs, Dan, Clark, Curtis, & Crawford, Doug. 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.  United States.  https://doi.org/10.1016/j.jnucmat.2017.07.047

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                    Keiser, Jr., Dennis D., Williams, Walter, Robinson, Adam, Wachs, Dan, Clark, Curtis, and Crawford, Doug. Thu .  
"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".  United States.  https://doi.org/10.1016/j.jnucmat.2017.07.047.  https://www.osti.gov/servlets/purl/1631701.

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@article{osti_1631701,

  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},

  author       = {Keiser, Jr., Dennis D. and Williams, Walter and Robinson, Adam and Wachs, Dan and Clark, Curtis and Crawford, Doug},

  abstractNote = {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.},

  doi          = {10.1016/j.jnucmat.2017.07.047},

  journal      = {Journal of Nuclear Materials},

  number       = C,

  volume       = 494,

  place        = {United States},

  year         = {Thu Jul 27 00:00:00 EDT 2017},

  month        = {Thu Jul 27 00:00:00 EDT 2017}

}

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Works referenced in this record:

IRRADIATION PERFORMANCE OF U-Mo MONOLITHIC FUEL
journal, April 2014

Meyer, M. K.; Gan, J.; Jue, J. F.
Nuclear Engineering and Technology, Vol. 46, Issue 2
DOI: 10.5516/NET.07.2014.706

Fission induced swelling of U–Mo/Al dispersion fuel
journal, October 2015

Kim, Yeon Soo; Jeong, G. Y.; Park, J. M.
Journal of Nuclear Materials, Vol. 465
DOI: 10.1016/j.jnucmat.2015.06.006

Swelling of U(Mo)–Al(Si) dispersion fuel under irradiation – Non-destructive analyses of the LEONIDAS E-FUTURE plates
journal, November 2012

Van den Berghe, S.; Parthoens, Y.; Charollais, F.
Journal of Nuclear Materials, Vol. 430, Issue 1-3
DOI: 10.1016/j.jnucmat.2012.06.045

Swelling of U(Mo) dispersion fuel under irradiation – Non-destructive analyses of the SELENIUM plates
journal, November 2013

Van den Berghe, S.; Parthoens, Y.; Cornelis, G.
Journal of Nuclear Materials, Vol. 442, Issue 1-3
DOI: 10.1016/j.jnucmat.2013.08.020

Swelling of U-7Mo/Al-Si dispersion fuel plates under irradiation – Non-destructive analysis of the AFIP-1 fuel plates
journal, August 2016

Wachs, D. M.; Robinson, A. B.; Rice, F. J.
Journal of Nuclear Materials, Vol. 476
DOI: 10.1016/j.jnucmat.2016.04.048

Effect of fission rate on the microstructure of coated UMo dispersion fuel
journal, October 2017

Leenaers, A.; Parthoens, Y.; Cornelis, G.
Journal of Nuclear Materials, Vol. 494
DOI: 10.1016/j.jnucmat.2017.06.036

Radiation Enhanced Diffusion in Solids
journal, December 1958

Dienes, G. J.; Damask, A. C.
Journal of Applied Physics, Vol. 29, Issue 12
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Radiation effects on solid state diffusion
journal, January 1975

Adda, Y.; Beyeler, M.; Brebec, G.
Thin Solid Films, Vol. 25, Issue 1
DOI: 10.1016/0040-6090(75)90251-5

Microstructural evolution of U(Mo)–Al(Si) dispersion fuel under irradiation – Destructive analyses of the LEONIDAS E-FUTURE plates
journal, October 2013

Leenaers, A.; Van den Berghe, S.; Van Eyken, J.
Journal of Nuclear Materials, Vol. 441, Issue 1-3
DOI: 10.1016/j.jnucmat.2013.06.027

Fuel swelling and interaction layer formation in the SELENIUM Si and ZrN coated U(Mo) dispersion fuel plates irradiated at high power in BR2
journal, March 2015

Leenaers, A.; Van den Berghe, S.; Koonen, E.
Journal of Nuclear Materials, Vol. 458
DOI: 10.1016/j.jnucmat.2014.12.073

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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

Abstract

Citation Formats

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