FFTF thermal-hydraulic testing results affecting piping and vessel component design in LMFBR's

Conference · Sat Jan 01 00:00:00 EST 1983

OSTI ID:5955897

Stover, R L; Beaver, T R; Chang, S C

The Fast Flux Test Facility completed four years of pre-operational testing in April 1982. This paper describes thermal-hydraulic testing results from this period which impact piping and vessel component design in LMFBRs. Data discussed are piping flow oscillations, piping thermal stratification and vessel upper plenum stratification. Results from testing verified that plant design limits were met.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 5955897
• Report Number(s): HEDL-SA-2762-FP; CONF-830607-22; ON: DE83015473
• Resource Relation: Conference: American Society of Mechanical Engineers pressure vessel and piping conference, Portland, OR, USA, 19 Jun 1983
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FFTF REACTOR
PRIMARY COOLANT CIRCUITS
REACTOR VESSELS
LMFBR TYPE REACTORS
HEAT TRANSFER
HYDRAULICS
PIPES
SPECIFICATIONS
TEMPERATURE GRADIENTS
BREEDER REACTORS
CONTAINERS
COOLING SYSTEMS
ENERGY SYSTEMS
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EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
LIQUID METAL COOLED REACTORS
MECHANICS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
210500* - Power Reactors
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220600 - Nuclear Reactor Technology- Research
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