Sensitivity Studies on UNF Cladding Structural Integrity under NCT Loading

Journal Article · Mon Dec 01 04:00:00 EST 2014 · Transactions of the American Nuclear Society

OSTI ID:1489402

Sanborn, Scott E. ^[1]; Koeppel, Brian J. ^[1]; Geelhood, Kenneth J. ^[1]; Adkins, Harold E. ^[1]

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1. BATTELLE (PACIFIC NW LAB)

This work describes the sensitivity analyses performed on the transportation package used in the NCT initial modeling and simulation demonstration [1]. The initial demonstration predicted the structural integrity of the fuel cladding by integrating models from the fuel rod/grid slot level, the single assembly-level, and the full cask-level. A number of sensitivity analyses were performed on the models at the different levels to determine how sensitive the results were to the parameters that were varied. The results are used to coarsely group the parameters investigated into four categories of sensitivity: No Sensitivity, Low Sensitivity; Moderate Sensitivity, and High Sensitivity. The High Sensitivity analyses are described in detail below. The Moderate, Low and No Sensitivity results are briefly described.

• Research Organization: Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-76RL01830
• OSTI ID: 1489402
• Report Number(s): PNNL-SA-104385
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 111; ISSN 0003-018X
• Publisher: American Nuclear Society
• Country of Publication: United States
• Language: English

Related Subjects

used nuclear fuel
UNF
normal conditions of transport
cladding integrity