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

Conference · Thu Jan 01 00:00:00 EST 1981

OSTI ID:6322451

Hoth, C W

Two full size highly instrumented fuel assemblies were inserted into the core of the Fast Flux Test Facility in December of 1979. The major objectives of these instrumented tests are to provide verification of the FFTF core conditions and to characterize temperature patterns within FFTF driver fuel assemblies. A review is presented of the results obtained during the power ascents and during irradiation at a constant reactor power of 400 MWt. The results obtained from these instrumented tests verify the conservative nature of the design methods used to establish core conditions in FFTF. The success of these tests also demonstrates the ability to design, fabricate, install and irradiate complex, instrumented fuel tests in FFTF using commercially procured components.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC14-76FF02170
• OSTI ID: 6322451
• Report Number(s): HEDL-SA-2330-Rev.1; CONF-810606-77(Rev.1); ON: DE81025295; TRN: 81-016037
• Resource Relation: 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
IN CORE INSTRUMENTS
ACCURACY
PERFORMANCE
TEMPERATURE DISTRIBUTION
THERMOCOUPLES
EPITHERMAL REACTORS
FAST REACTORS
LIQUID METAL COOLED REACTORS
MEASURING INSTRUMENTS
REACTOR INSTRUMENTATION
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors