Actions for Technical bases : FFTF fuel
Technical bases : FFTF fuel/cladding damage criteria
- Author
- Hanson, J. E.
- Published
- United States : [publisher not identified], 1970.
Springfield, Va. : National Technical Information Service, [approximately 1970] - Physical Description
- microfiche : negative ; 11 x 15 cm
- Additional Creators
- Ballard, E. O., Bard, Jr., F. E., Bullington, D. C., and Leggett, R. D.
- Summary
- Specification of fuel damage criteria is important in evaluating and verifying the adequacy of safety margins for the FFTF. These margins are provided to meet the established safety objectives for the facility. The purpose of this report is to review the parameter limits specified as preliminary design data in the FFTF design safety criteria, and to identify the bases for each of these limit values. These bases provide a logical framework for discussion of the uncertainties involved as well as emphasize the more promising options for maximizing the return on investment of development funds.
- Report Numbers
- BNWL-CC-2500
- Other Subject(s)
- 21 specific nuclear reactors and associated plants
- 220600 - nuclear reactor technology- research, test & experimental reactors
- Accidents
- Epithermal reactors
- Failures
- Fast reactors
- Fftf reactor
- Fuel cans
- Fuel elements
- Fuel pins
- Liquid metal cooled reactors
- Performance
- Reactor accidents
- Reactor components
- Reactors
- Research and test reactors
- Research reactors
- Sodium cooled reactors
- Stresses
- Temperature gradients
- Test reactors
- Collection
- NTIS collection.
- Note
- DOE contract number: EY-76-C-06-1830
OSTI Identifier 6798206
Research organization: Battelle Pacific Northwest Labs., Richland, WA (United States).
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