COBRA-SFS thermal-hydraulic analysis code for spent fuel storage and transportation casks: Models and methods

Journal Article · Fri Sep 01 00:00:00 EDT 2017 · Nuclear Technology

DOI:https://doi.org/10.1080/00295450.2017.1305190· OSTI ID:1349072

Michener, Thomas E. ^[1]; Rector, David R. ^[1]; Cuta, Judith M. ^[1]

---

1. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

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.

• Research Organization: Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
• Sponsoring Organization: USDOE
• Contributing Organization: Pacific Northwest National Laboratory
• Grant/Contract Number: AC05-76RL01830
• OSTI ID: 1349072
• Report Number(s): PNNL-SA-120387
• Journal Information: Nuclear Technology, Vol. 199, Issue 3; ISSN 0029-5450
• Publisher: Taylor & Francis - formerly American Nuclear Society (ANS)
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
spent nuclear fuel
COBRA-SFS
thermal-hydraulic modeling