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Title: A improved equation of state for Xe gas bubbles in γU-Mo fuels

Abstract

A monolithic fuel design based on a U-Mo alloy has been selected as the fuel type for conversion of the United States High-Performance Research Reactors (HPRRs). An issue with U-Mo monolithic fuel is the large amount of swelling that takes place during operation. The accurate prediction of fuel evolution under irradiation requires implementation of correct thermodynamic properties into mesoscale and continuum level fuel performance modeling codes. However, the thermodynamic properties of the fission gas bubbles (such as the relationship among bubble size, equilibrium Xe concentration, and bubble pressure) are not well known. This work studies Xe bubbles in ?U-Mo from a diameter of 3 nm up to 8.5 nm and from 400 K up to 700 K. The energetic relationship of Xe bubbles with regard to voids and Xe substitutional atoms is described. The transition is also determined for when a bubble becomes over-pressurized. Finally, an equation of state is fit to the pressure as a function of molar volume and temperature.

Authors:
ORCiD logo [1];  [2]; ORCiD logo [3]; ORCiD logo [3]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States); North Carolina State Univ., Raleigh, NC (United States)
  2. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
  3. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Energy Efficiency and Renewable Energy (EERE)
OSTI Identifier:
1631168
Alternate Identifier(s):
OSTI ID: 1580307
Report Number(s):
INL/JOU-19-54707-Rev000
Journal ID: ISSN 0022-3115
Grant/Contract Number:  
DE-AC07-05ID14517; AC07-05ID14517
Resource Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 530; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; uranium-molybdenum; molecular dynamics; fission gas bubbles; equation of state

Citation Formats

Beeler, Benjamin W, Hu, Shenyang, Zhang, Yongfeng, and Gao, Yipeng. A improved equation of state for Xe gas bubbles in γU-Mo fuels. United States: N. p., 2019. Web. https://doi.org/10.1016/j.jnucmat.2019.151961.
Beeler, Benjamin W, Hu, Shenyang, Zhang, Yongfeng, & Gao, Yipeng. A improved equation of state for Xe gas bubbles in γU-Mo fuels. United States. https://doi.org/10.1016/j.jnucmat.2019.151961
Beeler, Benjamin W, Hu, Shenyang, Zhang, Yongfeng, and Gao, Yipeng. Fri . "A improved equation of state for Xe gas bubbles in γU-Mo fuels". United States. https://doi.org/10.1016/j.jnucmat.2019.151961. https://www.osti.gov/servlets/purl/1631168.
@article{osti_1631168,
title = {A improved equation of state for Xe gas bubbles in γU-Mo fuels},
author = {Beeler, Benjamin W and Hu, Shenyang and Zhang, Yongfeng and Gao, Yipeng},
abstractNote = {A monolithic fuel design based on a U-Mo alloy has been selected as the fuel type for conversion of the United States High-Performance Research Reactors (HPRRs). An issue with U-Mo monolithic fuel is the large amount of swelling that takes place during operation. The accurate prediction of fuel evolution under irradiation requires implementation of correct thermodynamic properties into mesoscale and continuum level fuel performance modeling codes. However, the thermodynamic properties of the fission gas bubbles (such as the relationship among bubble size, equilibrium Xe concentration, and bubble pressure) are not well known. This work studies Xe bubbles in ?U-Mo from a diameter of 3 nm up to 8.5 nm and from 400 K up to 700 K. The energetic relationship of Xe bubbles with regard to voids and Xe substitutional atoms is described. The transition is also determined for when a bubble becomes over-pressurized. Finally, an equation of state is fit to the pressure as a function of molar volume and temperature.},
doi = {10.1016/j.jnucmat.2019.151961},
journal = {Journal of Nuclear Materials},
number = C,
volume = 530,
place = {United States},
year = {2019},
month = {12}
}

Journal Article:

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Cited by: 1 work
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