Title:
Drop, Fire, and Thermal Testing of a Nuclear Fuel Container
Author(s):
Frank J. Vecchio and James A. Sato
Publication:
Structural Journal
Volume:
85
Issue:
4
Appears on pages(s):
374-383
Keywords:
containment; conveying; density (mass/volume); fire tests; fuels; high-strength concretes; impact tests; irradiation; nuclear reactors; radiation shielding; reinforced concrete; storage; thermal gradient; wastes; weathering; Structural Research
DOI:
10.14359/2646
Date:
7/1/1988
Abstract:
Describes the structural testing performed on two half-scale models of a concrete cask proposed as a container for irradiated nuclear reactor fuel. The testing conducted on the first model was based on International Atomic Energy Agency regulations for licensing containers used to transport high-level radioactive materials. The tests consisted of a drop test from a height of 9 m (30 ft), followed by a 1 m (3.3 ft) drop onto a steel pin, followed by exposure to a severe fire condition. The second model was subjected to tests representing thermal loads encountered under normal service conditions. The cask models withstood all test conditions, retaining their structural integrity and providing full containment of the simulated payload. Significant cracking, spalling and crushing of concrete, and rupturing of reinforcing bars were experienced, however. The test program and the results are discussed, with emphasis on aspects pertaining to structural performance.