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Title: Correlation development for the interdiffusion layer growth in (U-Mo)/Al dispersion nuclear fuel.

Abstract

No abstract prepared.

Authors:
; ; ;
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
938609
Report Number(s):
ANL/NE/CP-119001
TRN: US0805982
DOE Contract Number:
DE-AC02-06CH11357
Resource Type:
Conference
Resource Relation:
Conference: 2nd International Conference on Diffusion in Solids and Liquids; Jul. 26, 2006 - Jul. 28, 2006; Aveiro - Portugal
Country of Publication:
United States
Language:
ENGLISH
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; DIFFUSION; DISPERSION NUCLEAR FUELS; ANL

Citation Formats

Kim, Y. S., Hofman, G. L., Ryu, H. J., and Nuclear Engineering Division. Correlation development for the interdiffusion layer growth in (U-Mo)/Al dispersion nuclear fuel.. United States: N. p., 2006. Web.
Kim, Y. S., Hofman, G. L., Ryu, H. J., & Nuclear Engineering Division. Correlation development for the interdiffusion layer growth in (U-Mo)/Al dispersion nuclear fuel.. United States.
Kim, Y. S., Hofman, G. L., Ryu, H. J., and Nuclear Engineering Division. Sun . "Correlation development for the interdiffusion layer growth in (U-Mo)/Al dispersion nuclear fuel.". United States. doi:.
@article{osti_938609,
title = {Correlation development for the interdiffusion layer growth in (U-Mo)/Al dispersion nuclear fuel.},
author = {Kim, Y. S. and Hofman, G. L. and Ryu, H. J. and Nuclear Engineering Division},
abstractNote = {No abstract prepared.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jan 01 00:00:00 EST 2006},
month = {Sun Jan 01 00:00:00 EST 2006}
}

Conference:
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  • The interaction layer (IL) growth correlation of (U-Mo)/Al dispersion fuel for in-reactor tests is considerably different from that for out-of-pile tests because it contains factors that enhance diffusion kinetics by fission damage in the IL. This enhancement during irradiation was formulated by a combination of the fission rate and fission-fragment damage factor in the IL. Using a computer code (TRIM), fission damage factors were obtained as a function of the thickness and Al-composition of the IL. As a result of data fitting, the model correlation was set as a function of four major factors: fission rate, fission-damage factors, temperature andmore » time. One important change from the old model used in the PLATE code is that the new one has the squareroot dependence on the fission rate, whereas the old one has a linear dependence. The preliminary PIE results from RERTR-6 have shown a significant reduction in the IL thickness for the Si-added plates as well as prevention of pore formation. The reduction in IL growth followed an exponential decay function of the Si-content.« less
  • As a remedy for reducing reaction between U-Mo and Al in U-Mo/Al dispersion fuel, adding an alloying element such as Zr and Ti in U-Mo has been proposed at ANL. Although ANL's work showed the potential effectiveness of these elements based on thermodynamic and metallurgical analyses, the effect of a Ti addition in U-Mo remains unproven. The out-of-pile tests of U-Mo-Ti alloys, which focused on phase stability and interdiffusion behavior against Al, are meaningful to predict their efficacy during an irradiation. At the 2006 RERTR conference, we presented our work on the interdiffusion behaviors of U-Mo-Zr/Al-Si. In this paper, wemore » will present the results for substituting U-Mo-Zr with U-Mo-Ti. Unlike U-Mo-Zr alloys, the gamma-heat-treated U-7Mo-xTi (x=1-3 wt%) exhibited a metastable ?-U phase, regardless of the Ti content. In these samples, however, a small amount of second-phase precipitates with a high Ti concentration was observed. The gamma phase stability of the U-Mo-Ti alloys at 500 C was similar to that of the U-Mo-Zr alloys. Interdiffusion test results between U-Mo-Ti alloys and Al-Si alloys will also be presented and a comparison with the previous results with U-Mo-Zr/Al-Si will also be included.« less
  • As a remedy for reducing reaction between U-Mo and Al in U-Mo/Al dispersion fuel, adding an alloying element such as Zr and Ti in U-Mo has been proposed at ANL. Although ANL's work showed the potential effectiveness of these elements based on thermodynamic and metallurgical analyses, the effect of a Ti addition in U-Mo remains unproven. The out-of-pile tests of U-Mo-Ti alloys, which focused on phase stability and interdiffusion behavior against Al, are meaningful to predict their efficacy during an irradiation. At the 2006 RERTR conference, we presented our work on the interdiffusion behaviors of U-Mo-Zr/Al-Si. In this paper, wemore » will present the results for substituting U-Mo-Zr with U-Mo-Ti. Unlike U-Mo-Zr alloys, the gamma-heat-treated U-7Mo-xTi (x=1{approx}3 wt%) exhibited a metastable {gamma}-U phase, regardless of the Ti content. In these samples, however, a small amount of second-phase precipitates with a high Ti concentration was observed. The gamma phase stability of the U-Mo-Ti alloys at 500 deg C was similar to that of the U-Mo-Zr alloys. Interdiffusion test results between U-Mo-Ti alloys and Al-Si alloys will also be presented and a comparison with the previous results with U- Mo-Zr/Al-Si will also be included. (author)« less