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Title: Thermal testing of a dry spent fuel cask. [NL1 /sup 1///sub 2/ legal weight truck cask]

Conference ·
OSTI ID:6681889

A nuclear spent fuel cask that employs air or an inert gas such as helium as the cooling medium in the fuel cavity is commonly known as a ''dry'' cask. The thermal characteristics of a dry cask differ considerably from a wet cask. A gas is a poorer heat transfer medium than water. As a result, the fuel and cask basket temperatures will be higher for a given fuel heat level. The response characteristics during operating transients will also differ. Detailed thermal tests on a dry cask were performed to verify design parameters and to obtain operational data for shipping and unloading. Results of a number of thermal tests performed on the NL1 /sup 1///sub 2/ legal weight truck cask are presented. The uniqueness of these tests are that they were performed using a full-scale geometric and thermal mockup of a nuclear fuel assembly. This results in more realistic fuel and basket temperatures being measured than those obtained using a simpler, single heater assembly.

Research Organization:
Allied-General Nuclear Services, Barnwell, SC (USA)
DOE Contract Number:
ET-78-C-09-1040
OSTI ID:
6681889
Report Number(s):
AGNS-1040-12; CONF-780506-26; TRN: 78-016328
Resource Relation:
Conference: 5. symposium on packaging and transportation of radioactive materials, Las Vegas, NV, USA, 7 May 1978
Country of Publication:
United States
Language:
English