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Title: Modeling the influence of interaction layer formation on thermal conductivity of U–Mo dispersion fuel

Authors:
; ;
Publication Date:
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1249617
Resource Type:
Journal Article: Publisher's Accepted Manuscript
Journal Name:
Journal of Alloys and Compounds
Additional Journal Information:
Journal Volume: 618; Journal Issue: C; Related Information: CHORUS Timestamp: 2016-09-04 20:43:36; Journal ID: ISSN 0925-8388
Publisher:
Elsevier
Country of Publication:
Netherlands
Language:
English

Citation Formats

Burkes, Douglas E., Casella, Andrew M., and Huber, Tanja K. Modeling the influence of interaction layer formation on thermal conductivity of U–Mo dispersion fuel. Netherlands: N. p., 2015. Web. doi:10.1016/j.jallcom.2014.08.123.
Burkes, Douglas E., Casella, Andrew M., & Huber, Tanja K. Modeling the influence of interaction layer formation on thermal conductivity of U–Mo dispersion fuel. Netherlands. doi:10.1016/j.jallcom.2014.08.123.
Burkes, Douglas E., Casella, Andrew M., and Huber, Tanja K. Thu . "Modeling the influence of interaction layer formation on thermal conductivity of U–Mo dispersion fuel". Netherlands. doi:10.1016/j.jallcom.2014.08.123.
@article{osti_1249617,
title = {Modeling the influence of interaction layer formation on thermal conductivity of U–Mo dispersion fuel},
author = {Burkes, Douglas E. and Casella, Andrew M. and Huber, Tanja K.},
abstractNote = {},
doi = {10.1016/j.jallcom.2014.08.123},
journal = {Journal of Alloys and Compounds},
number = C,
volume = 618,
place = {Netherlands},
year = {Thu Jan 01 00:00:00 EST 2015},
month = {Thu Jan 01 00:00:00 EST 2015}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record at 10.1016/j.jallcom.2014.08.123

Citation Metrics:
Cited by: 2works
Citation information provided by
Web of Science

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  • The Global Threat Reduction Initiative Program continues to develop existing and new plate- and rod-type research and test reactor fuels with maximum attainable uranium loadings capable of potentially converting a number of the world’s remaining high-enriched uranium fueled reactors to low-enriched uranium fuel. Currently, the program is focused on assisting with the development and qualification of an even higher density fuel type consisting of a uranium-molybdenum (U-Mo) alloy dispersed in an aluminum matrix. Thermal conductivity is an important consideration in determining the operational temperature of the fuel plate and can be influenced by interaction layer formation between the fuel andmore » matrix, porosity that forms during fabrication of the fuel plates, and upon the concentration of the dispersed phase within the matrix. This paper develops and validates a simple model to study the influence of interaction layer formation and conductivity, fuel particle size, and volume fraction of fuel dispersed in the matrix on the effective conductivity of the composite. The model shows excellent agreement with results previously presented in the literature. In particular, the thermal conductivity of the interaction layer does not appear to be important in determining the overall conductivity of the composite, while formation of the interaction layer and subsequent consumption of the matrix reveals a rather significant effect. The effective thermal conductivity of the composite can be influenced by the fuel particle distribution by minimizing interaction layer formation and preserving the higher thermal conductivity matrix.« less
  • Post irradiation examinations of full-size U-Mo/Al dispersion fuel plates fabricated with ZrN- or Sicoated U-Mo particles revealed that the reaction rate of irradiation-induced U-Mo-Al inter-diffusion, an important microstructural change impacting the performance of this type of fuel, is temperature and fission-rate dependent. In order to simulate the U-Mo/Al inter-diffusion layer (IL) growth behavior in full-size dispersion fuel plates, the existing IL growth correlation was modified with a temperaturedependent multiplication factor that transits around a threshold fission rate. In-pile irradiation data from four tests in the BR2 reactors, including FUTURE, E-FUTURE, SELEMIUM, and SELEMIUM-1a, were utilized to determine and validate themore » updated IL growth correlation. Irradiation behavior of the plates was simulated with the DART-2D computational code. The general agreement between the calculated and measured fuel meat swelling and constituent volume fractions as a function of fission density demonstrated the plausibility of the updated IL growth correlation. The simulation results also suggested the temperature dependence of the IL growth rate, similar to the temperature dependence of the intermixing rate in ion-irradiated bi-layer systems.« less