Analysis of in-core coolant temperatures of FFTF instrumented fuels tests at full power

Conference · Thu Jan 01 00:00:00 EST 1981 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5047877

Hoth, C W

• Research Organization: Westinghouse Hanford, Richland, WA 99352
• OSTI ID: 5047877
• Report Number(s): CONF-810606-
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Vol. 38; Conference: American Nuclear Society's annual meeting, Miami Beach, FL, USA, 7 Jun 1981
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FFTF REACTOR
FUEL ASSEMBLIES
TEMPERATURE MEASUREMENT
COMPUTER CODES
COOLANTS
FLOWMETERS
NEUTRON FLUX
TESTING
THERMOCOUPLES
EPITHERMAL REACTORS
FAST REACTORS
LIQUID METAL COOLED REACTORS
MEASURING INSTRUMENTS
METERS
RADIATION FLUX
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors