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Operational safety report for the cleaning of non-radioactive, sodium-wetted reactor components with ethyl alcohol [electronic resource].

Published
Downey, Calif : Rockwell International, 1974.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Additional Creators
Rockwell International and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
The safety aspects of the removal of sodium from nonradioactive reactor components by the alcohol process are described in detail. Pertinent properties of alcohol and hydrogen are presented. Relevant excerpts from the Occupational Safety and Health Act safety codes are presented, and a conceptual system is shown illustrating the application of these safety measures.
Report Numbers
E 1.99:doe/sf/91001-t2
doe/sf/91001-t2
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
01/01/1974.
"doe/sf/91001-t2"
"DE81026176"
Humphrey, L.; Felton, L.; Goodman, L.; Pilicy, G.; Welch, F.
Funding Information
AT03-76SF91001
View MARC record | catkey: 14368443