Power Burst Facility

Technical Report · Sun Jan 01 04:00:00 EST 1984

DOI:https://doi.org/10.2172/5145968· OSTI ID:5145968

Experimental programs for the PBF have focused on light water reactor safety research for typical power reactor fuel rods under normal, off-normal, and accident conditions. The PBF reactor and test loop provide the capability to conduct experiments to simulate reactivity initiated accidents, power-cooling-mismatch accidents, anticipated transients with and without scram, loss-of-coolant accidents, and severe fuel damage accidents using clusters of up to 32 test fuel rods. Measurements of test rod coolant conditions, cladding and fuel temperatures, internal rod pressure, rod elongation, and other data are recorded on magnetic tape during the PBF experiments. A sophisticated sampling and monitoring system makes it possible to determine the time-dependent release of fission products. A test train assembly facility provides capabilities to fabricate, instrument, and assemble irradiated and unirradiated test assemblies.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5145968
• Report Number(s): EGG-B-332-0384-.5M; ON: DE84009471
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
PBF REACTOR
POWER REACTORS
PULSED REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR EXPERIMENTAL FACILITIES
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
TANK TYPE REACTORS
WATER COOLED REACTORS