K-Reactor [electronic resource] : Loss of coolant temperature study of the biological skin
- Published
- Washington, D.C. : United States. Dept. of Energy, 1967.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- 9 pages : digital, PDF file
- Additional Creators
- United States. Department of Energy and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- It is of interest to investigate the time following a complete loss of coolant incident when the pile would be exposed to the ambient air. This is of concern due to the fast propagation of graphite burn-up when brought in contact with air at or above the operating temperature of the graphite (1292°F). One possible way conjectured in which the pile can be exposed to the surrounding environment is for the centering flange gasket (neoprene) or the bellows gas seal (silicone) to fail. This particular study was concerned with the temperature transient of the seals following the extreme accident condition of complete loss of coolant. This problem is one of many being investigated in a concentrated effort to re-evaluate the effectiveness of the confinement system of the smaller reactors. The maximum credible accident for the DUN operated production reactors has been the loss of coolant to a single cross header. The Hanford philosophy of reactor safety has been the provision of reliable methods of cooling fuel in all accident situations short of severance of the primary coolant piping or destruction of the reactor building. However, for the present study the more serious accident of complete loss of coolant was investigated. This far exceeds the postulated maximum credible accident stated above, so therefore the results will be based on a highly hypothetical situation. The fuel melt time following a complete loss of coolant and the corresponding heat-up of the graphite has already been investigated. A computer code (TIGER-5) was used to calculate the temperature transient of the biological and thermal shield region following the loss of coolant accident.
- Report Numbers
- E 1.99:dun--3247
dun--3247 - Subject(s)
- Other Subject(s)
- Note
- Published through SciTech Connect.
10/13/1967.
"dun--3247"
"DE94016984"
White, J.A.
Douglas United Nuclear, Inc., Richland, WA (United States) - Type of Report and Period Covered Note
- Topical; 10/01/1967 - 10/01/1967
- Funding Information
- AC06-76RL01830
View MARC record | catkey: 14370304