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Title: Thermo-mechanical performance assessment of selected plates from MP-1 low power experiments

Abstract

Monolithic plate-type fuel is a fuel form that is being developed for the conversion of high performance research and test reactors to low-enrichment uranium fuels. These fuel-plates are comprised of a high density, low enrichment, U-Mo alloy based fuel foil encapsulated in an aluminum cladding. To benchmark this new design, number of plates has been irradiated with satisfactory performance. As a part of continuing evaluation efforts, a set of plates covering range of operational parameters is scheduled to be tested during MP-1 irradiation experiments. It is necessary to evaluate the thermo-mechanical performance of plates during irradiation. For this, selected plates with distinct operational histories; covering low power, high power and high fission density were simulated. Fully coupled three-dimensional models of plates with a capability to evolve mechanical and thermal properties of constituent materials with irradiation time and burn-up were developed. The models input used projected parameters, including plate geometry, irradiation history and coolant conditions as input. The model output included temperature, displacement and stresses in the fuel, cladding and diffusion barrier. The fuel behavioral model considered inelastic behavior including volumetric swelling due to solid and gaseous products, irradiation induced creep, thermal expansion, conductivity degradation and plasticity. A visco-plastic behavioral modelmore » was used for the cladding that included thermal creep, irradiation hardening, growth due to fast neutrons and Mises plasticity. The plates were then simulated by using projected irradiation parameters. The resulting temperature, displacement and stress-strains were comparatively evaluated on the selected paths. The results were then compared with those of plates from previous RERTR experiments.« less

Authors:
ORCiD logo [1];  [1]
  1. Idaho National Laboratory
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1484449
Report Number(s):
INL/CON-18-51101-Rev000
DOE Contract Number:  
AC07-05ID14517
Resource Type:
Conference
Resource Relation:
Conference: IMECE2018, International Mechanical Engineering Congress & Exposition, Pittsburgh, PA, 11/09/2018 - 11/15/2018
Country of Publication:
United States
Language:
English
Subject:
42 - ENGINEERING; U-Mo; monolithic fuel plate; irradiation; MP-1

Citation Formats

Ozaltun, Hakan, and Rabin, Barry H. Thermo-mechanical performance assessment of selected plates from MP-1 low power experiments. United States: N. p., 2018. Web.
Ozaltun, Hakan, & Rabin, Barry H. Thermo-mechanical performance assessment of selected plates from MP-1 low power experiments. United States.
Ozaltun, Hakan, and Rabin, Barry H. Fri . "Thermo-mechanical performance assessment of selected plates from MP-1 low power experiments". United States. doi:. https://www.osti.gov/servlets/purl/1484449.
@article{osti_1484449,
title = {Thermo-mechanical performance assessment of selected plates from MP-1 low power experiments},
author = {Ozaltun, Hakan and Rabin, Barry H},
abstractNote = {Monolithic plate-type fuel is a fuel form that is being developed for the conversion of high performance research and test reactors to low-enrichment uranium fuels. These fuel-plates are comprised of a high density, low enrichment, U-Mo alloy based fuel foil encapsulated in an aluminum cladding. To benchmark this new design, number of plates has been irradiated with satisfactory performance. As a part of continuing evaluation efforts, a set of plates covering range of operational parameters is scheduled to be tested during MP-1 irradiation experiments. It is necessary to evaluate the thermo-mechanical performance of plates during irradiation. For this, selected plates with distinct operational histories; covering low power, high power and high fission density were simulated. Fully coupled three-dimensional models of plates with a capability to evolve mechanical and thermal properties of constituent materials with irradiation time and burn-up were developed. The models input used projected parameters, including plate geometry, irradiation history and coolant conditions as input. The model output included temperature, displacement and stresses in the fuel, cladding and diffusion barrier. The fuel behavioral model considered inelastic behavior including volumetric swelling due to solid and gaseous products, irradiation induced creep, thermal expansion, conductivity degradation and plasticity. A visco-plastic behavioral model was used for the cladding that included thermal creep, irradiation hardening, growth due to fast neutrons and Mises plasticity. The plates were then simulated by using projected irradiation parameters. The resulting temperature, displacement and stress-strains were comparatively evaluated on the selected paths. The results were then compared with those of plates from previous RERTR experiments.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Nov 09 00:00:00 EST 2018},
month = {Fri Nov 09 00:00:00 EST 2018}
}

Conference:
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