Improvement and verification of fast reactor safety analysis techniques. Progress report, January 1, 1978--March 31, 1978
- Author
- Barker, D. H.
- Published
- United States : [publisher not identified], 1978.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1978. - Physical Description
- microfiche : negative ; 11 x 15 cm
- Additional Creators
- Wheeler, P. A.
- Summary
- A stainless steel vessel was used to perform preliminary fuel simulant, closed system experiments. The reaction of DMSO in acetyl chloride was carried out within the closed vessel. Temperatures and pressure in the vessel were measured as a function of time for several solution concentrations. These experiments are the first of a series deigned to investigate the properties of fuel dispersion in a closed system.
- Report Numbers
- COO-2571-12
- Other Subject(s)
- 21 specific nuclear reactors and associated plants
- 210500 - power reactors, breeding
- 22 general studies of nuclear reactors
- 220900 - nuclear reactor technology- reactor safety
- Accidents
- Breeder reactors
- Epithermal reactors
- Fast reactors
- Fbr type reactors
- Liquid metal cooled reactors
- Lmfbr type reactors
- Meltdown
- Pressure gradients
- Reactor accidents
- Reactor core disruption
- Reactors
- Simulation
- Temperature distribution
- Collection
- U.S. Atomic Energy Commission depository collection.
- Note
- DOE contract number: EY-76-S-02-2571
OSTI Identifier 7038564
Research organization: Brigham Young Univ., Provo, Utah (USA). Dept. of Chemical Engineering. - Funding Information
- Sponsored by USDOE.
View MARC record | catkey: 44280329