Analysis of in-core-coolant temperature distributions within FFTF instrumented fuel assemblies

Conference · Fri Jan 01 00:00:00 EST 1982

OSTI ID:5059915

Hoth, C W

Instrumented fuel assembly tests are installed in the Fast Flux Test Facility and are monitoring in-core coolant temperatures. Comparison of measured temperature data to calculated temperatures from a thermal-hydraulic code confirms the validity of the thermal-hydraulic models.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 5059915
• Report Number(s): HEDL-SA-2624-FP; CONF-820903-7; ON: DE82016159; TRN: 82-018873
• Resource Relation: Conference: ANS topical meeting, Niagara Falls, NY, USA, 22 Sep 1982
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FFTF REACTOR
IN CORE INSTRUMENTS
TEMPERATURE MONITORING
FUEL ASSEMBLIES
TEMPERATURE DISTRIBUTION
THERMOCOUPLES
EPITHERMAL REACTORS
FAST REACTORS
LIQUID METAL COOLED REACTORS
MEASURING INSTRUMENTS
MONITORING
REACTOR INSTRUMENTATION
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors