Structural analysis of the source term transportation cask

Technical Report · Tue Oct 01 00:00:00 EDT 1991

OSTI ID:5649813

Hoffman, E L; Attaway, S W

Structural calculations were performed to evaluate the source-term nuclear fuels transport cask (ST Cask) under various hypothetical accident scenarios. (1) Three-dimensional transient dynamic analyses were performed to evaluate the strength of the cask's end-closure clamp mechanism. The calculations were performed for two impact orientations: a side impact and a 20{degrees} corner impact. The calculations identified three weaknesses in the clamp design: a gap designed between the clamp and the cask provides a deformation mode which loosens the clamp, two unconstrained swing bolts used to fasten the clamp can lose preload and come free; and insufficient stiffness of the clamp in torsion. (2) An axisymmetric finite element model was used to evaluate the dynamics of end-drops from 5 and 10 ft. The calculations show that loads generated in the end-drops could break the payload support cable and damage the payload winch. Lead slump resulted in both end-drop calculations. The stresses generated in the cask wall during the end-drops was insufficient to cause buckling. (3) To determine the factor of safety to yield, calculations in which the cask was treated as a beam loaded under its own weight were performed for two support configurations: simply supported at both ends and simply supported at the center (trunnion loading). (4) The survival of the cask from a 1-m drop onto a mild steel punch was evaluated based on equations derived from empirical data. The calculations showed that the ST Cask could survive such an event. (5) Finally, the bolt configuration for the upper-closure was analyzed and determined to be inadequate because it does not prevent the closure from sliding relative to the cask body. Specific recommendations for design changes are made in the report to eliminate identified problems.

• Research Organization: Sandia National Labs., Albuquerque, NM (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 5649813
• Report Number(s): SAND-91-1543; ON: DE92010400
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
CASKS
A CODES
F CODES
G CODES
M CODES
STRESS ANALYSIS
MECHANICAL PROPERTIES
P CODES
NUCLEAR FUELS
CONTAINMENT
CLOSURES
COMPUTER GRAPHICS
DESIGN BASIS ACCIDENTS
DYNAMIC LOADS
FAILURES
FINITE ELEMENT METHOD
IMPACT STRENGTH
MATHEMATICAL MODELS
MESH GENERATION
PERFORMANCE TESTING
RADIATION PROTECTION
RADIOACTIVE MATERIALS
SAFETY ANALYSIS
SOURCE TERMS
STATIC LOADS
STRUCTURAL BEAMS
TRANSPORT
TRANSPORT REGULATIONS
YIELD STRENGTH
ACCIDENTS
COMPUTER CODES
CONTAINERS
ENERGY SOURCES
FUELS
MATERIALS
NUMERICAL SOLUTION
REACTOR ACCIDENTS
REACTOR MATERIALS
REGULATIONS
TESTING
050900* - Nuclear Fuels- Transport
Handling
& Storage
420203 - Engineering- Handling Equipment & Procedures
990200 - Mathematics & Computers