Repository logo
Log In(current)
  1. Home
  2. Colleges & Schools
  3. Graduate School
  4. Masters Theses
  5. Sensitivity Analysis of Fuel Cladding Temperature to Dry Cask Loading and Storage Conditions
Details

Sensitivity Analysis of Fuel Cladding Temperature to Dry Cask Loading and Storage Conditions

Date Issued
August 1, 2015
Author(s)
DeVoe, Remy Russell  
Advisor(s)
Steven E. Skutnik
Additional Advisor(s)
G. Ivan Maldonado, Arthur E. Ruggles
Abstract

Dry cask safety analyses and material degradation studies depend on reliable best- estimate thermal models. Gaps in design data and storage site conditions require analysts to frequently rely on bounding assumptions in thermal models that introduce bias to the results. Efforts to gather physical attributes of cask designs from vendors or experimental measurements can be costly and to determine all the uncertain parameters for a number of different cask designs is impractical. Measuring the sensitivity of peak cladding temperature to cask and fuel depletion modeling parameters was done to inform decision makers of which parameters that have the most impact on temperature predictions and should be further investigated. This study is applicable to vertical multi-purpose canister systems for long-term storage evaluations such as those done for an interim storage facility. The most sensitive cask parameters are those that affect convective heat transfer in the cask annulus and within the canister basket. These parameters are the ambient air temperature, canister pressure, and assembly decay heat profile with measured sensitivity coefficients of 0.50, -0.2841, and 0.0767, respectively. The sensitivity of peak cladding temperature to reactor cycle history was measured, and the most sensitive parameter was burnup, but other reactor operating history variations had little impact on temperature predictions.

Subjects

Thermal Modeling

Used Nuclear Fuel

Sensitivity Analysis

Nuclear Reactors

Dry Cask Storage

MAGNASTOR

Cladding Temperature

Disciplines
Nuclear Engineering
Degree
Master of Science
Major
Nuclear Engineering
Embargo Date
January 1, 2011
File(s)
Thumbnail Image
Name

Devoe_Thesis.pdf

Size

2.24 MB

Format

Adobe PDF

Checksum (MD5)

30ab3a95e72d0de11eca2bf7e2769951

Built with DSpace-CRIS software - Extension maintained and optimized by 4Science

  • Privacy policy
  • End User Agreement
  • Send Feedback
  • Contact
  • Libraries at University of Tennessee, Knoxville
Repository logo COAR Notify