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

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.
Authors:
Publication Date:
OSTI Identifier:
6322451
Report Number(s):
HEDL-SA-2330-Rev.1; CONF-810606-77(Rev.1)
ON: DE81025295; TRN: 81-016037
DOE Contract Number:
AC14-76FF02170
Resource Type:
Conference
Resource Relation:
Conference: American Nuclear Society's annual meeting, Miami Beach, FL, USA, 7 Jun 1981
Research Org:
Hanford Engineering Development Lab., Richland, WA (USA)
Country of Publication:
United States
Language:
English
Subject:
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