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Title: Use of multiscale zirconium alloy deformation models in nuclear fuel behavior analysis

Abstract

Accurate prediction of cladding mechanical behavior is a key aspect of modeling nuclear fuel behavior, especially for conditions of pellet-cladding interaction (PCI), reactivity-initiated accidents (RIA), and loss of coolant accidents (LOCA). Current approaches to fuel performance modeling rely on empirical models for cladding creep, growth and plastic deformation, which are limited to the materials and conditions for which the models were developed. CASL has endeavored to improve upon this approach by incorporating a microstructurally-based, atomistically-informed, zirconium alloy mechanical deformation analysis capability into the BISON-CASL engineering scale fuel performance code. Specifically, the viscoplastic self-consistent (VPSC) polycrystal plasticity modeling approach, developed by Lebensohn and Tome´ [2], has been coupled with BISON-CASL to represent the mechanistic material processes controlling the deformation behavior of the cladding. A critical component of VPSC is the representation of the crystallographic orientation of the grains within the matrix material and the ability to account for the role of texture on deformation. The multiscale modeling of cladding deformation mechanisms allowed by VPSC far exceed the functionality of typical semi-empirical constitutive models employed in nuclear fuel behavior codes to model irradiation growth and creep, thermal creep, or plasticity. This paper describes the implementation of an interface between VPSC and BISON-CASLmore » and provides initial results utilizing the coupled functionality.« less

Authors:
ORCiD logo; ; ; ; ORCiD logo;
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1339025
Report Number(s):
PNNL-SA-107715
Journal ID: ISSN 0021-9991; 830403000
DOE Contract Number:  
AC05-76RL01830
Resource Type:
Journal Article
Journal Name:
Journal of Computational Physics
Additional Journal Information:
Journal Volume: 328; Journal Issue: C; Journal ID: ISSN 0021-9991
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Citation Formats

Montgomery, Robert, Tomé, Carlos, Liu, Wenfeng, Alankar, Alankar, Subramanian, Gopinath, and Stanek, Christopher. Use of multiscale zirconium alloy deformation models in nuclear fuel behavior analysis. United States: N. p., 2017. Web. doi:10.1016/j.jcp.2016.09.051.
Montgomery, Robert, Tomé, Carlos, Liu, Wenfeng, Alankar, Alankar, Subramanian, Gopinath, & Stanek, Christopher. Use of multiscale zirconium alloy deformation models in nuclear fuel behavior analysis. United States. doi:10.1016/j.jcp.2016.09.051.
Montgomery, Robert, Tomé, Carlos, Liu, Wenfeng, Alankar, Alankar, Subramanian, Gopinath, and Stanek, Christopher. Sun . "Use of multiscale zirconium alloy deformation models in nuclear fuel behavior analysis". United States. doi:10.1016/j.jcp.2016.09.051.
@article{osti_1339025,
title = {Use of multiscale zirconium alloy deformation models in nuclear fuel behavior analysis},
author = {Montgomery, Robert and Tomé, Carlos and Liu, Wenfeng and Alankar, Alankar and Subramanian, Gopinath and Stanek, Christopher},
abstractNote = {Accurate prediction of cladding mechanical behavior is a key aspect of modeling nuclear fuel behavior, especially for conditions of pellet-cladding interaction (PCI), reactivity-initiated accidents (RIA), and loss of coolant accidents (LOCA). Current approaches to fuel performance modeling rely on empirical models for cladding creep, growth and plastic deformation, which are limited to the materials and conditions for which the models were developed. CASL has endeavored to improve upon this approach by incorporating a microstructurally-based, atomistically-informed, zirconium alloy mechanical deformation analysis capability into the BISON-CASL engineering scale fuel performance code. Specifically, the viscoplastic self-consistent (VPSC) polycrystal plasticity modeling approach, developed by Lebensohn and Tome´ [2], has been coupled with BISON-CASL to represent the mechanistic material processes controlling the deformation behavior of the cladding. A critical component of VPSC is the representation of the crystallographic orientation of the grains within the matrix material and the ability to account for the role of texture on deformation. The multiscale modeling of cladding deformation mechanisms allowed by VPSC far exceed the functionality of typical semi-empirical constitutive models employed in nuclear fuel behavior codes to model irradiation growth and creep, thermal creep, or plasticity. This paper describes the implementation of an interface between VPSC and BISON-CASL and provides initial results utilizing the coupled functionality.},
doi = {10.1016/j.jcp.2016.09.051},
journal = {Journal of Computational Physics},
issn = {0021-9991},
number = C,
volume = 328,
place = {United States},
year = {2017},
month = {1}
}