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:
-
[1];
[3];
[3]
- Idaho National Lab. (INL), Idaho Falls, ID (United States); North Carolina State Univ., Raleigh, NC (United States)
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Publication Date:
- Research Org.:
- Idaho National Laboratory (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; TRN: US2200756
- 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. doi: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 = {Fri Dec 20 00:00:00 EST 2019},
month = {Fri Dec 20 00:00:00 EST 2019}
}
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