Actions for ORNL NUCLEAR SAFETY RESEARCH AND DEVELOPMENT PROGRAM BIMONTHLY REPORT FOR MARCH--APRIL 1971
ORNL NUCLEAR SAFETY RESEARCH AND DEVELOPMENT PROGRAM BIMONTHLY REPORT FOR MARCH--APRIL 1971
- Author
- Cottrell, W. B.
- Published
- United States : [publisher not identified], 1971.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1971. - Physical Description
- microfiche : negative ; 11 x 15 cm
- Report Numbers
- ORNL-TM-3411
- Other Subject(s)
- Accidents- coating- containment shells- hydrogen- loss of coolant- paints- production- water cooled reactors
- Accidents- failures- fuel cans- loss of coolant- reactor safety- water cooled reactors- zircaloy
- Coated fuel particles- distribution- fission products- gas cooled reactors
- Configuration- failures- nozzles- pipes- pressure vessels- pumps- steels- stresses- valves
- Corrosion- graphite- steam- temperature- testing
- Failures- fuel elements- lmfbr- testing
- Fission products/release from gas cooled coated particle fuels
- Graphite/corrosion of h327, by high temperature steam, (e).
- Hydrogen/production in water cooled reactor containment structures, effects of coolant loss accident conditions on.
- Information- information retrieval- reactor safety
- N38160 -power reactor development-auxiliary & emergency systems
- N38180 -power reactor development-safety & siting
- Nozzles/stresses in reactor pressure vessel, effects of attachment configuration on, (e/t).
- Pipe fittings/elastic response and fatigue testing of, for nuclear service
- Pipes/design criteria for nuclear service, development program for
- Pressure vessels/fracture of heavy section steel, (e).
- Pressure vessels/nozzles of, effects of attachment configuration on stresses in, (e/t).
- Reactor fuel elements/failu
- Reactor fuels/fission product release from gas cooled coated particles
- Reactors, gas-cooled/fuels of, fission product release from coated particles
- Reactors, water-cooled/ standards for, development of engineering
- Reactors, water-cooled/coolant loss accidents in, hydrogen generation and control during
- Standards- water cooled reactors
- Steam/corrosive effects on h327 graphite, (e).
- Collection
- U.S. Atomic Energy Commission depository collection.
- Note
- DOE contract number: W-7405-ENG-26
NSA number: NSA-25-048291
OSTI Identifier 4712352
Research organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). - Funding Information
- Sponsored by USDOE.
View MARC record | catkey: 46150732