WATER-COOLED NUCLEAR REACTORS AND HEAT TRANSFER CRISIS AT BOILING. (in Russian)
Technical Report
·
OSTI ID:4828706
- Research Organization:
- Gosudarstvennyi Komitet po Ispol'zovaniyu Atomnoi Energii SSSR, Obninsk. Fiziko-Energeticheskii Institut
- NSA Number:
- NSA-23-004204
- OSTI ID:
- 4828706
- Report Number(s):
- FEI--111
- Country of Publication:
- Country unknown/Code not available
- Language:
- Russian
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Related Subjects
BOILING
BOILING/critical heat flux in water- cooled reactors
review of analysis methods for
BURNOUT
COOLANT LOOPS
CRITICAL HEAT FLUX
HEAT TRANSFER
HEAT TRANSFER/critical heat flux in boiling-water forced-flow channels
review of analysis methods for
HIGH TEMPERATURE
N38140* --Power Reactor Development--Cooling Systems
REACTORS
REACTORS
BOILING/cooling systems of
review of critical heat flux analysis methods for
REACTORS
WATER-COOLED/cooling systems of
review of critical heat flux analysis methods for
WATER COOLANT
BOILING/critical heat flux in water- cooled reactors
review of analysis methods for
BURNOUT
COOLANT LOOPS
CRITICAL HEAT FLUX
HEAT TRANSFER
HEAT TRANSFER/critical heat flux in boiling-water forced-flow channels
review of analysis methods for
HIGH TEMPERATURE
N38140* --Power Reactor Development--Cooling Systems
REACTORS
REACTORS
BOILING/cooling systems of
review of critical heat flux analysis methods for
REACTORS
WATER-COOLED/cooling systems of
review of critical heat flux analysis methods for
WATER COOLANT