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.; Kraft, N. C.; Taylor, S. C.; Lillo, M.; Woolstenhulme, N.; Roth, G. A.

doi:10.1016/j.jnucmat.2016.04.048

Title: Swelling of U-7Mo/Al-Si dispersion fuel plates under irradiation – Non-destructive analysis of the AFIP-1 fuel plates

Full Record
Other Related Research

Authors:: Wachs, D. M.; Robinson, A. B.; Rice, F. J.; Kraft, N. C.; Taylor, S. C.; Lillo, M.; Woolstenhulme, N.; Roth, G. A.

Publication Date:: Mon Aug 01 00:00:00 EDT 2016

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

OSTI Identifier:: 1359421

Grant/Contract Number:: AC07-05ID14517

Resource Type:: Publisher's Accepted Manuscript

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Name: Journal of Nuclear Materials Journal Volume: 476 Journal Issue: C; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: Netherlands

Language:: English

Citation Formats


                    Wachs, D. M., Robinson, A. B., Rice, F. J., Kraft, N. C., Taylor, S. C., Lillo, M., Woolstenhulme, N., and Roth, G. A. Swelling of U-7Mo/Al-Si dispersion fuel plates under irradiation – Non-destructive analysis of the AFIP-1 fuel plates.  Netherlands: N. p., 2016. 
Web.  doi:10.1016/j.jnucmat.2016.04.048.

Copy to clipboard


                    Wachs, D. M., Robinson, A. B., Rice, F. J., Kraft, N. C., Taylor, S. C., Lillo, M., Woolstenhulme, N., & Roth, G. A. Swelling of U-7Mo/Al-Si dispersion fuel plates under irradiation – Non-destructive analysis of the AFIP-1 fuel plates.  Netherlands.  https://doi.org/10.1016/j.jnucmat.2016.04.048

Copy to clipboard


                    Wachs, D. M., Robinson, A. B., Rice, F. J., Kraft, N. C., Taylor, S. C., Lillo, M., Woolstenhulme, N., and Roth, G. A. Mon .  
"Swelling of U-7Mo/Al-Si dispersion fuel plates under irradiation – Non-destructive analysis of the AFIP-1 fuel plates".  Netherlands.  https://doi.org/10.1016/j.jnucmat.2016.04.048.

Copy to clipboard


                    
@article{osti_1359421,

  title        = {Swelling of U-7Mo/Al-Si dispersion fuel plates under irradiation – Non-destructive analysis of the AFIP-1 fuel plates},

  author       = {Wachs, D. M. and Robinson, A. B. and Rice, F. J. and Kraft, N. C. and Taylor, S. C. and Lillo, M. and Woolstenhulme, N. and Roth, G. A.},

  abstractNote = {},

  doi          = {10.1016/j.jnucmat.2016.04.048},

  journal      = {Journal of Nuclear Materials},

  number       = C,

  volume       = 476,

  place        = {Netherlands},

  year         = {Mon Aug 01 00:00:00 EDT 2016},

  month        = {Mon Aug 01 00:00:00 EDT 2016}

}

Copy to clipboard

Journal Article:

Free Publicly Available Full Text

Accepted Manuscript (Publisher)

Publisher's Version of Record
https://doi.org/10.1016/j.jnucmat.2016.04.048

Other availability

Search WorldCat to find libraries that may hold this journal

Citation Metrics:

Cited by: 14 works

Citation information provided by
Web of Science

Save / Share:

Export Metadata

Save to My Library

Similar Records in DOE PAGES and OSTI.GOV collections:

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

Journal Article den Berghe, S Van ; Parthoens, Y ; Charollais, F ; ... - Journal of Nuclear Materials

In the framework of the elimination of High-Enriched Uranium (HEU) from the civil circuit, the search for an appropriate fuel to replace the high-enriched research reactor fuel in those reactors that currently still require it for their operation has led to the development of a U–7 wt.%Mo alloy based dispersion fuel with an Al–Si matrix. The European LEONIDAS program, joining SCK-CEN, ILL, CEA and AREVA-CERCA, is aimed at the qualification of such a fuel for the use in high power conditions. The first experiment of the program, designated E-FUTURE, was performed to select the appropriate matrix Si concentration and fuelmore »« less
https://doi.org/10.1016/j.jnucmat.2012.06.045
Microstructural evolution of U(Mo)–Al(Si) dispersion fuel under irradiation – Destructive analyses of the LEONIDAS E-FUTURE plates

Journal Article Leenaers, A. ; S. Van den Berghe ; Eyken, J. Van ; ... - Journal of Nuclear Materials

Several irradiation experiments have confirmed the positive effect of adding Si to the matrix of an U(Mo) dispersion fuel plate on its in-pile irradiation behavior. E-FUTURE, the first experiment of the LEONIDAS program, was performed to select an optimum Si concentration and fuel plate heat treatment parameters for further qualification. It consisted of the irradiation of 4 distinct (regarding Si content and heat treatments), full size flat fuel plates in the BR2 reactor under bounding conditions (470 W/cm2 peak BOL power, approximately 70% peak burn-up). After the irradiation, the E-FUTURE plates were examined non-destructively and found to have pillowed inmore »« less
https://doi.org/10.1016/j.jnucmat.2013.06.027
Irradiation performance of a U-7Mo in Al-Si matrix dispersion full-size fuel plate assembly

Journal Article Woolstenhulme, Nicolas E. ; Robinson, Adam B. ; Nielsen, Joseph W. ; ... - Nuclear Engineering and Design

The Korea Atomic Energy Research Institute (KAERI) is leading the Ki-Jang Research Reactor (KJRR) project with the intent to develop a new reactor for medical isotope production and other nuclear research purposes. The KJRR core is designed to use high density fuel system where uranium alloyed with 7 wt% molybdenum (U-7Mo) particles are dispersed in a matrix of aluminum alloyed with 5 wt% silicon (Al-5Si) and clad in aluminum alloy 6061 (Al-6061) to form fuel plates. KAERI developed a fabrication facility to construct KJRR fuel assemblies and partnered with the Idaho National Laboratory (INL) to irradiate a full-size fuel assembly,more »« less
https://doi.org/10.1016/j.nucengdes.2023.112761
Microstructural Characterization of U-7Mo/Al-Si Alloy Matrix Dispersion Fuel Plates Fabricated at 500°C

Journal Article Keiser, Jr, Dennis D ; Jue, Jan-Fong ; Yao, Bo ; ... - Journal of Nuclear Materials

The starting microstructure of a dispersion fuel plate will impact the overall performance of the plate during irradiation. To improve the understanding of the as-fabricated microstructures of U–Mo dispersion fuel plates, particularly the interaction layers that can form between the fuel particles and the matrix, scanning electron microscopy (SEM) and transmission electron microscopy (TEM) analyses have been performed on samples from depleted U–7Mo (U–7Mo) dispersion fuel plates with either Al–2 wt.% Si(Al–2Si) or AA4043 alloy matrix. It was observed that in the thick interaction layers, U(Al, Si)3 and U6Mo4Al43 were present, and in the thin interaction layers, (U, Mo) (Al,more »« less
https://doi.org/10.1016/j.jnucmat.2011.02.027
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 Keiser, Jr., Dennis D. ; Williams, Walter ; Robinson, Adam ; ... - Journal of Nuclear Materials

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,more »« less
Cited by 6
https://doi.org/10.1016/j.jnucmat.2017.07.047

Full Text Available

Similar Records