COBRA-SFS thermal-hydraulic analysis code for spent fuel storage and transportation casks: Models and methods
Abstract
COBRA-SFS, a thermal-hydraulics code developed for steady-state and transient analysis of multi-assembly spent-fuel storage and transportation systems, has been incorporated into the Used Nuclear Fuel-Storage, Transportation and Disposal Analysis Resource and Data System tool as a module devoted to spent fuel package thermal analysis. This paper summarizes the basic formulation of the equations and models used in the COBRA-SFS code, showing that COBRA-SFS fully captures the important physical behavior governing the thermal performance of spent fuel storage systems, with internal and external natural convection flow patterns, and heat transfer by convection, conduction, and thermal radiation. Of particular significance is the capability for detailed thermal radiation modeling within the fuel rod array.
- Authors:
-
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Publication Date:
- Research Org.:
- Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
- Sponsoring Org.:
- USDOE
- Contributing Org.:
- Pacific Northwest National Laboratory
- OSTI Identifier:
- 1349072
- Report Number(s):
- PNNL-SA-120387
Journal ID: ISSN 0029-5450
- Grant/Contract Number:
- AC05-76RL01830
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Nuclear Technology
- Additional Journal Information:
- Journal Volume: 199; Journal Issue: 3; Journal ID: ISSN 0029-5450
- Publisher:
- Taylor & Francis - formerly American Nuclear Society (ANS)
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; spent nuclear fuel; COBRA-SFS; thermal-hydraulic modeling
Citation Formats
Michener, Thomas E., Rector, David R., and Cuta, Judith M. COBRA-SFS thermal-hydraulic analysis code for spent fuel storage and transportation casks: Models and methods. United States: N. p., 2017.
Web. doi:10.1080/00295450.2017.1305190.
Michener, Thomas E., Rector, David R., & Cuta, Judith M. COBRA-SFS thermal-hydraulic analysis code for spent fuel storage and transportation casks: Models and methods. United States. https://doi.org/10.1080/00295450.2017.1305190
Michener, Thomas E., Rector, David R., and Cuta, Judith M. Fri .
"COBRA-SFS thermal-hydraulic analysis code for spent fuel storage and transportation casks: Models and methods". United States. https://doi.org/10.1080/00295450.2017.1305190. https://www.osti.gov/servlets/purl/1349072.
@article{osti_1349072,
title = {COBRA-SFS thermal-hydraulic analysis code for spent fuel storage and transportation casks: Models and methods},
author = {Michener, Thomas E. and Rector, David R. and Cuta, Judith M.},
abstractNote = {COBRA-SFS, a thermal-hydraulics code developed for steady-state and transient analysis of multi-assembly spent-fuel storage and transportation systems, has been incorporated into the Used Nuclear Fuel-Storage, Transportation and Disposal Analysis Resource and Data System tool as a module devoted to spent fuel package thermal analysis. This paper summarizes the basic formulation of the equations and models used in the COBRA-SFS code, showing that COBRA-SFS fully captures the important physical behavior governing the thermal performance of spent fuel storage systems, with internal and external natural convection flow patterns, and heat transfer by convection, conduction, and thermal radiation. Of particular significance is the capability for detailed thermal radiation modeling within the fuel rod array.},
doi = {10.1080/00295450.2017.1305190},
journal = {Nuclear Technology},
number = 3,
volume = 199,
place = {United States},
year = {Fri Sep 01 00:00:00 EDT 2017},
month = {Fri Sep 01 00:00:00 EDT 2017}
}
Web of Science
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Works referencing / citing this record:
Thermal Analysis of dry Storage and Transportation Casks Castor Using Cobra-Sfs
journal, December 2020
- Ševeček, Martin; Valach, Mojmír; Lee, Chih-Hao
- Acta Polytechnica CTU Proceedings, Vol. 28