Development and validation of capabilities to measure thermal properties of layered monolithic U-Mo alloy plate-type fuel
Abstract
The uranium-molybdenum (U-Mo) alloy in a monolithic form has been proposed as one fuel design capable of converting some of the world’s highest power research reactors from the use of high enriched uranium (HEU) to low enriched uranium (LEU). One aspect of the fuel development and qualification process is to demonstrate appropriate understanding of thermal conductivity behavior of the fuel system as a function of temperature and expected irradiation conditions. The purpose of this paper is to verify and validate the functionality of equipment methods installed in hot cells for eventual measurements on irradiated uranium-molybdenum (U-Mo) monolithic fuel specimens, procedures to operate the equipment, and models to extract the desired thermal properties. The results presented here demonstrate the adequacy of the equipment, procedures and models that have been developed for this purpose based on measurements conducted on surrogate depleted uranium-molybdenum (DU-Mo) alloy samples containing a zirconium diffusion barrier and clad in aluminum alloy 6061 (AA6061). The results are in excellent agreement with thermal property data reported in the literature for similar U-Mo alloys as a function of temperature.
- Authors:
- Publication Date:
- Research Org.:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1171282
- Report Number(s):
- PNNL-SA-100138
NN9100000
- DOE Contract Number:
- AC05-76RL01830
- Resource Type:
- Journal Article
- Journal Name:
- International Journal of Thermophysics, 35(8):1476-1500
- Additional Journal Information:
- Journal Name: International Journal of Thermophysics, 35(8):1476-1500
- Country of Publication:
- United States
- Language:
- English
- Subject:
- nuclear fuel; uranium-molybdenum; multi-layer; thermal conductivity
Citation Formats
Burkes, Douglas, Casella, Andrew M., Buck, Edgar C., Casella, Amanda J., Edwards, Matthew K., MacFarlan, Paul J., Pool, Karl N., Smith, Frances N., and Steen, Franciska H. Development and validation of capabilities to measure thermal properties of layered monolithic U-Mo alloy plate-type fuel. United States: N. p., 2014.
Web. doi:10.1007/s10765-014-1683-4.
Burkes, Douglas, Casella, Andrew M., Buck, Edgar C., Casella, Amanda J., Edwards, Matthew K., MacFarlan, Paul J., Pool, Karl N., Smith, Frances N., & Steen, Franciska H. Development and validation of capabilities to measure thermal properties of layered monolithic U-Mo alloy plate-type fuel. United States. https://doi.org/10.1007/s10765-014-1683-4
Burkes, Douglas, Casella, Andrew M., Buck, Edgar C., Casella, Amanda J., Edwards, Matthew K., MacFarlan, Paul J., Pool, Karl N., Smith, Frances N., and Steen, Franciska H. 2014.
"Development and validation of capabilities to measure thermal properties of layered monolithic U-Mo alloy plate-type fuel". United States. https://doi.org/10.1007/s10765-014-1683-4.
@article{osti_1171282,
title = {Development and validation of capabilities to measure thermal properties of layered monolithic U-Mo alloy plate-type fuel},
author = {Burkes, Douglas and Casella, Andrew M. and Buck, Edgar C. and Casella, Amanda J. and Edwards, Matthew K. and MacFarlan, Paul J. and Pool, Karl N. and Smith, Frances N. and Steen, Franciska H.},
abstractNote = {The uranium-molybdenum (U-Mo) alloy in a monolithic form has been proposed as one fuel design capable of converting some of the world’s highest power research reactors from the use of high enriched uranium (HEU) to low enriched uranium (LEU). One aspect of the fuel development and qualification process is to demonstrate appropriate understanding of thermal conductivity behavior of the fuel system as a function of temperature and expected irradiation conditions. The purpose of this paper is to verify and validate the functionality of equipment methods installed in hot cells for eventual measurements on irradiated uranium-molybdenum (U-Mo) monolithic fuel specimens, procedures to operate the equipment, and models to extract the desired thermal properties. The results presented here demonstrate the adequacy of the equipment, procedures and models that have been developed for this purpose based on measurements conducted on surrogate depleted uranium-molybdenum (DU-Mo) alloy samples containing a zirconium diffusion barrier and clad in aluminum alloy 6061 (AA6061). The results are in excellent agreement with thermal property data reported in the literature for similar U-Mo alloys as a function of temperature.},
doi = {10.1007/s10765-014-1683-4},
url = {https://www.osti.gov/biblio/1171282},
journal = {International Journal of Thermophysics, 35(8):1476-1500},
number = ,
volume = ,
place = {United States},
year = {Sat Jul 19 00:00:00 EDT 2014},
month = {Sat Jul 19 00:00:00 EDT 2014}
}