Development and calibration of an aerosol monitor used for PBF (Power Burst Facility) Test SFD (severe fuel damage) 1-4

Conference · Wed Jan 01 00:00:00 EST 1986

OSTI ID:6497559

Adams, J P; Partin, J K; Petti, D A; Reed, T R

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
• Resource Relation: Conference: 4. Miami international symposium on multi-phase transport and particulate phenomena, Miami Beach, FL, USA, 15 Dec 1986; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
MONITORS
CALIBRATION
DESIGN
RADIOACTIVE AEROSOLS
AEROSOL MONITORING
WATER COOLED REACTORS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
CONTROL ELEMENTS
DENSITOMETERS
FIBER OPTICS
FISSION PRODUCT RELEASE
FISSION PRODUCTS
FUEL CANS
PBF REACTOR
REACTOR CORES
ACCIDENTS
AEROSOLS
AIR POLLUTION MONITORING
COLLOIDS
DISPERSIONS
ISOTOPES
MATERIALS
MEASURING INSTRUMENTS
MONITORING
PHOTOMETERS
PULSED REACTORS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTORS
SOLS
TANK TYPE REACTORS
220502* - Nuclear Reactor Technology- Environmental Aspects- Radioactive Effluents
220900 - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
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Light-Water Moderated
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