Breached fuel location in FFTF by delayed neutron monitor triangulation
Conference
·
OSTI ID:6195013
The Fast Flux Test Facility (FFTF) features a three-loop, sodium-cooled 400 MWt mixed oxide fueled reactor designed for the irradiation testing of fuels and materials for use in liquid metal cooled fast reactors. To establish the ultimate capability of a particular fuel design and thereby generate information that will lead to improvements, many of the fuel irradiations are continued until a loss of cladding integrity (failure) occurs. When the cladding fails, fission gas escapes from the fuel pin and enters the reactor cover gas system. If the cladding failure permits the primary sodium to come in contact with the fuel, recoil fission products can enter the sodium. The presence of recoil fission products in the sodium can be detected by monitoring for the presence of delayed neutrons in the coolant. It is the present philosophy to not operate FFTF when a failure has occurred that permits fission fragments to enter the sodium. Thus, it is important that the identity and location of the fuel assembly that contains the failed cladding be established in order that it might be removed from the core. This report discusses method of location of fuel element when cladding is breached.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 6195013
- Report Number(s):
- HEDL-SA-3324; CONF-851115-55; ON: DE89010133
- Country of Publication:
- United States
- Language:
- English
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·
OSTI ID:7142359
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900 -- Nuclear Reactor Technology-- Reactor Safety
COOLING SYSTEMS
ENERGY SYSTEMS
EPITHERMAL REACTORS
FAILURES
FAST REACTORS
FFTF REACTOR
FISSION PRODUCT RELEASE
FUEL CANS
FUEL ELEMENTS
LIQUID METAL COOLED REACTORS
MEASURING INSTRUMENTS
NEUTRON DETECTORS
RADIATION DETECTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MONITORING SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM COOLED REACTORS
TEST REACTORS
210500* -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900 -- Nuclear Reactor Technology-- Reactor Safety
COOLING SYSTEMS
ENERGY SYSTEMS
EPITHERMAL REACTORS
FAILURES
FAST REACTORS
FFTF REACTOR
FISSION PRODUCT RELEASE
FUEL CANS
FUEL ELEMENTS
LIQUID METAL COOLED REACTORS
MEASURING INSTRUMENTS
NEUTRON DETECTORS
RADIATION DETECTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MONITORING SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM COOLED REACTORS
TEST REACTORS