FFTF primary system transition to natural circulation from low reactor power

Conference · Tue Jan 01 00:00:00 EST 1980

OSTI ID:5505997

Bouchey, G. D.; Additon, S. L.; Nutt, W. T.

Plans for reactor and primary loop natural circulation testing in the Fast Flux Test Facility (FFTF) are summarized. Detailed pretest planning with an emphasis on understanding the implications of process noise and model uncertainties for model verification and test acceptance are discussed for a transition to natural circulation in the reactor core and primary heat transport loops from initial conditions of 5% of rated reactor power and 75% of full flow.

• Research Organization: Department of Energy, Richland, WA (USA). Richland Operations Office; Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: EY-76-C-14-2170
• OSTI ID: 5505997
• Report Number(s): HEDL-SA-1919-FP; CONF-800226-4; TRN: 80-007967
• Resource Relation: Conference: Specialists meeting on decay heat removal and natural circulation in FBR's, Upton, NY, USA, 28 Feb 1980
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FFTF REACTOR
AFTER-HEAT REMOVAL
LOSS OF FLOW
AFTER-HEAT
HEAT TRANSFER
NATURAL CONVECTION
PRIMARY COOLANT CIRCUITS
REACTOR SAFETY
ACCIDENTS
CONVECTION
COOLING SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
LIQUID METAL COOLED REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
REMOVAL
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM COOLED REACTORS
TEST REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors