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Title: Analysis of constituent redistribution in U-Pu-Zr metallic fuel.

Abstract

No abstract prepared.

Authors:
; ; ; ;
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
921879
Report Number(s):
ANL/NE/JA-55045
Journal ID: ISSN 0022-3115; JNUMAM; TRN: US0800787
DOE Contract Number:
DE-AC02-06CH11357
Resource Type:
Journal Article
Resource Relation:
Journal Name: J. Nucl. Mater.; Journal Volume: 359; Journal Issue: 1 ; 2006
Country of Publication:
United States
Language:
ENGLISH
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; ALLOY NUCLEAR FUELS; DISTRIBUTION; URANIUM; PLUTONIUM; ZIRCONIUM

Citation Formats

Kim, Y. S., Hofman, G. L., Yacout, A. M., Nuclear Engineering Division, and A.M. Yacout. Analysis of constituent redistribution in U-Pu-Zr metallic fuel.. United States: N. p., 2006. Web. doi:10.1016/j.jnucmat.2006.07.013.
Kim, Y. S., Hofman, G. L., Yacout, A. M., Nuclear Engineering Division, & A.M. Yacout. Analysis of constituent redistribution in U-Pu-Zr metallic fuel.. United States. doi:10.1016/j.jnucmat.2006.07.013.
Kim, Y. S., Hofman, G. L., Yacout, A. M., Nuclear Engineering Division, and A.M. Yacout. Sun . "Analysis of constituent redistribution in U-Pu-Zr metallic fuel.". United States. doi:10.1016/j.jnucmat.2006.07.013.
@article{osti_921879,
title = {Analysis of constituent redistribution in U-Pu-Zr metallic fuel.},
author = {Kim, Y. S. and Hofman, G. L. and Yacout, A. M. and Nuclear Engineering Division and A.M. Yacout},
abstractNote = {No abstract prepared.},
doi = {10.1016/j.jnucmat.2006.07.013},
journal = {J. Nucl. Mater.},
number = 1 ; 2006,
volume = 359,
place = {United States},
year = {Sun Jan 01 00:00:00 EST 2006},
month = {Sun Jan 01 00:00:00 EST 2006}
}
  • The Advanced Fuels Campaign (AFC) metallic fuels currently being tested have higher zirconium and plutonium concentrations than those tested in the past in EBR reactors. Current metal fuel performance codes have limitations and deficiencies in predicting AFC fuel performance, particularly in the modeling of constituent distribution. No fully validated code exists due to sparse data and unknown modeling parameters. Our primary objective is to develop an initial analysis tool by incorporating state-of-the-art knowledge, constitutive models and properties of AFC metal fuels into the MOOSE/BISON (1) framework in order to analyze AFC metallic fuel tests.
  • A computer model was developed to analyze constituent redistribution in U-Pu-Zr metallic nuclear fuels. Diffusion and thermochemical properties were parametrically determined to fit the postirradiation data from a fuel test performed in the Experimental Breeder Reactor II (EBR-II). The computer model was used to estimate redistribution profiles of fuels proposed for the conceptual designs of small modular fast reactors. The model results showed that the level of redistribution of the fuel constituents of the designs was similar to the measured data from EBR-II.
  • Irradiation and fission-related phenomena in metallic fuels based on the U-Pu-Zr system result in fuel restructuring in the forms of fuel swelling (Xe/Kr bubble growth) and constituent redistribution. An experiment designed to analyze the early development of these phenomena and the correlative behavior between them has recently been completed. Fuel porosity development was traced carefully as a function of fuel burnup. The results indicate that the porosity distributions would lead to significant changes in fuel operating temperature. Concurrent observations concerning composition redistribution indicate that the porosity development preceded significant constituent redistribution. The zirconium redistribution had been theorized to be relatedmore » to the position of phase boundaries at specific locations within the thermal gradients existing in the fuel. The restructuring phenomena are analyzed in terms of how they may affect the existence of specific phases and, therefore, atomic migration.« less
  • A model for constituent migration behavior in U-Pu-Zr metallic fast reactor fuel is proposed. It is based on diffusion equations for the ternary system under a radial temperature gradient, and it takes into account the alloy phase decomposition, assuming a quasi-binary U-Zr phase diagram with a constant plutonium content. Parametric simulations of Experimental Breeder Reactor II irradiation data with appropriate transport properties of the alloy system showed that the model can predict the experimentally observed radial three-zone structure and zirconium and uranium redistribution, although the predicted radial location of zirconium-depleted middle zone disagreed with the experimental result. Accumulation of basicmore » experimental data on transport properties and a ternary phase diagram of the system are needed for a better understanding of the behavior.« less