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U.S. Department of Energy
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A method for determining the spent-fuel contribution to transport cask containment requirements

Technical Report ·
OSTI ID:6971263
;  [1]; ;  [2];  [3];  [4];  [5];
  1. Sandia National Labs., Albuquerque, NM (United States)
  2. ANATECH Research Corp., La Jolla, CA (United States)
  3. Oak Ridge National Lab., TN (United States)
  4. Pacific Northwest Lab., Richland, WA (United States)
  5. EG and G Rocky Flats, Inc., Golden, CO (United States). Rocky Flats Plant

This report examines containment requirements for spent-fuel transport containers that are transported under normal and hypothetical accident conditions. A methodology is described that estimates the probability of rod failure and the quantity of radioactive material released from breached rods. This methodology characterizes the dynamic environment of the cask and its contents and deterministically models the peak stresses that are induced in spent-fuel cladding by the mechanical and thermal dynamic environments. The peak stresses are evaluated in relation to probabilistic failure criteria for generated or preexisting ductile tearing and material fractures at cracks partially through the wall in fuel rods. Activity concentrations in the cask cavity are predicted from estimates of the fraction of gases, volatiles, and fuel fines that are released when the rod cladding is breached. Containment requirements based on the source term are calculated in terms of maximum permissible volumetric leak rates from the cask. Calculations are included for representative cask designs.

Research Organization:
Sandia National Labs., Albuquerque, NM (United States)
Sponsoring Organization:
DOE; USDOE, Washington, DC (United States)
DOE Contract Number:
AC04-76DP00789
OSTI ID:
6971263
Report Number(s):
SAND-90-2406; TTC--1019; ON: DE93004596
Country of Publication:
United States
Language:
English