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Title: ASSESSMENT OF RESIDUAL STRESSES ON U10MO ALLOY BASED MONOLITHIC MINI-PLATES DURING HOT ISOSTATIC PRESSING

Abstract

This article presents an assessment of the residual stress field on U10Mo alloy based monolithic fuel plates and their elasto-plastic response to the thermo-mechanical fabrication process. Monolithic plate-type fuel for research and test reactors is a new fuel form proposed and developed by Idaho National Laboratory (INL) to accomplish higher uranium densities in the reactor core and allow multi-fold reduction of fuel enrichment. Identification of the 3D residual field is critical for benchmarking the new design and understanding the overall performance of the new plate-type fuels. To define fuel-cladding stress-strain characteristics, a new thermo-mechanical finite element model was developed. Material properties at high temperatures and material plasticity were considered carefully to improve the accuracy as the Hot Pressing temperature reaches the melting temperature of the cladding material. By using elasto-thermo-plastic material models, it was determined that the cladding material (AL6061-TO) is exposed to tensile stress field and exceeds its proportional limits, while the fuel foil (U10Mo) is under compression and remains below its yield limit. It was shown that the residual stresses would govern the overall behavior of the plates, and therefore, should not be neglected. In particular, the simulations have revealed the existence of stress gradients at the fuel/claddingmore » interface, thus emphasizing the necessity of excellent bonding quality at the bond region for mechanical endurance.« less

Authors:
;
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
DOE - NA
OSTI Identifier:
1035215
Report Number(s):
INL/JOU-11-21753
Journal ID: ISSN 0022-3115; JNUMAM; TRN: US1200994
DOE Contract Number:  
DE-AC07-05ID14517
Resource Type:
Journal Article
Resource Relation:
Journal Name: Journal of Nuclear Materials; Journal Volume: 419; Journal Issue: 1 - 3
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 42 ENGINEERING; ACCURACY; ALLOYS; BONDING; COMPRESSION; DESIGN; FABRICATION; FUEL PLATES; HOT PRESSING; IDAHO NATIONAL LABORATORY; MELTING; PERFORMANCE; PLASTICITY; PLATES; REACTOR CORES; RESEARCH AND TEST REACTORS; RESIDUAL STRESSES; URANIUM; Finite Element Analysis; Hot Isostatic Pressing; Residual Stresses

Citation Formats

Hakan Ozaltun, and M.-H. Herman Shen. ASSESSMENT OF RESIDUAL STRESSES ON U10MO ALLOY BASED MONOLITHIC MINI-PLATES DURING HOT ISOSTATIC PRESSING. United States: N. p., 2011. Web. doi:10.1016/j.jnucmat.2011.08.029.
Hakan Ozaltun, & M.-H. Herman Shen. ASSESSMENT OF RESIDUAL STRESSES ON U10MO ALLOY BASED MONOLITHIC MINI-PLATES DURING HOT ISOSTATIC PRESSING. United States. doi:10.1016/j.jnucmat.2011.08.029.
Hakan Ozaltun, and M.-H. Herman Shen. Thu . "ASSESSMENT OF RESIDUAL STRESSES ON U10MO ALLOY BASED MONOLITHIC MINI-PLATES DURING HOT ISOSTATIC PRESSING". United States. doi:10.1016/j.jnucmat.2011.08.029.
@article{osti_1035215,
title = {ASSESSMENT OF RESIDUAL STRESSES ON U10MO ALLOY BASED MONOLITHIC MINI-PLATES DURING HOT ISOSTATIC PRESSING},
author = {Hakan Ozaltun and M.-H. Herman Shen},
abstractNote = {This article presents an assessment of the residual stress field on U10Mo alloy based monolithic fuel plates and their elasto-plastic response to the thermo-mechanical fabrication process. Monolithic plate-type fuel for research and test reactors is a new fuel form proposed and developed by Idaho National Laboratory (INL) to accomplish higher uranium densities in the reactor core and allow multi-fold reduction of fuel enrichment. Identification of the 3D residual field is critical for benchmarking the new design and understanding the overall performance of the new plate-type fuels. To define fuel-cladding stress-strain characteristics, a new thermo-mechanical finite element model was developed. Material properties at high temperatures and material plasticity were considered carefully to improve the accuracy as the Hot Pressing temperature reaches the melting temperature of the cladding material. By using elasto-thermo-plastic material models, it was determined that the cladding material (AL6061-TO) is exposed to tensile stress field and exceeds its proportional limits, while the fuel foil (U10Mo) is under compression and remains below its yield limit. It was shown that the residual stresses would govern the overall behavior of the plates, and therefore, should not be neglected. In particular, the simulations have revealed the existence of stress gradients at the fuel/cladding interface, thus emphasizing the necessity of excellent bonding quality at the bond region for mechanical endurance.},
doi = {10.1016/j.jnucmat.2011.08.029},
journal = {Journal of Nuclear Materials},
number = 1 - 3,
volume = 419,
place = {United States},
year = {Thu Dec 01 00:00:00 EST 2011},
month = {Thu Dec 01 00:00:00 EST 2011}
}