Development and calibration of an aerosol monitor used for PBF (Power Burst Facility) Test SFD (severe fuel damage) 1-4
Conference
·
OSTI ID:6497559
An understanding of fission product behavior during a severe core damage accident in a light water reactor is required to accurately predict the resultant radiological source term to the environment. An internationally sponsored series of four severe fuel damage (SFD) experiments was conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory to characterize fission product release and transport from severely damaged nuclear fuel. The last experiment, SFD 1-4, was designed to study the behavior of fission products and aerosols generated from control rod, fuel rod cladding, and core structural materials. An on-line aerosol monitor was developed and installed in the test effluent line to study the time-dependent aerosol transport behavior during the experiment. The aerosol monitor consisted of two turbidity meters, used in series, to measure the attenuation of light caused by aerosols in the effluent stream. The outputs from these two attenuation cells were then used to determine the aerosol number density. The high-pressure, high-temperature, and high-radiation field environment of Test SFD 1-4 represented a unique and challenging application for this type of transducer and necessitated considerable development and testing. This paper describes the design and calibration of the aerosol monitor and discusses how the aerosol measurement results were used to aid in the interpretation of Test SFD 1-4.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6497559
- Report Number(s):
- EGG-M-31086; CONF-861204-8; ON: DE87009402
- Country of Publication:
- United States
- Language:
- English
Similar Records
Results from the Power Burst Facility Severe Fuel Damage Test 1-4
Fission product behavior during the in-pile Severe Fuel Damage Test SFD 1-4
Power Burst Facility (PBF) severe fuel damage test 1-4 test results report
Conference
·
Thu Dec 31 23:00:00 EST 1987
·
OSTI ID:6534324
Fission product behavior during the in-pile Severe Fuel Damage Test SFD 1-4
Conference
·
Thu Dec 31 23:00:00 EST 1987
·
OSTI ID:6565253
Power Burst Facility (PBF) severe fuel damage test 1-4 test results report
Technical Report
·
Fri Mar 31 23:00:00 EST 1989
·
OSTI ID:5983389
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220502* -- Nuclear Reactor Technology-- Environmental Aspects-- Radioactive Effluents
220900 -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AEROSOL MONITORING
AEROSOLS
AIR POLLUTION MONITORING
CALIBRATION
COLLOIDS
CONTROL ELEMENTS
DENSITOMETERS
DESIGN
DISPERSIONS
FIBER OPTICS
FISSION PRODUCT RELEASE
FISSION PRODUCTS
FUEL CANS
ISOTOPES
MATERIALS
MEASURING INSTRUMENTS
MONITORING
MONITORS
PBF REACTOR
PHOTOMETERS
PULSED REACTORS
RADIOACTIVE AEROSOLS
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR CORES
REACTORS
SOLS
TANK TYPE REACTORS
WATER COOLED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220502* -- Nuclear Reactor Technology-- Environmental Aspects-- Radioactive Effluents
220900 -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AEROSOL MONITORING
AEROSOLS
AIR POLLUTION MONITORING
CALIBRATION
COLLOIDS
CONTROL ELEMENTS
DENSITOMETERS
DESIGN
DISPERSIONS
FIBER OPTICS
FISSION PRODUCT RELEASE
FISSION PRODUCTS
FUEL CANS
ISOTOPES
MATERIALS
MEASURING INSTRUMENTS
MONITORING
MONITORS
PBF REACTOR
PHOTOMETERS
PULSED REACTORS
RADIOACTIVE AEROSOLS
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR CORES
REACTORS
SOLS
TANK TYPE REACTORS
WATER COOLED REACTORS