Release and deposition of volatile fission products during in-pile severe fuel damage tests
Conference
·
OSTI ID:5387883
Four in-pile Severe Fuel Damage (SFD) tests have been conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory (INEL). These tests are part of the Severe Fuel Damage Source Term Research Program sponsored by the United States Nuclear Regulatory Commission and its international partners. The overall objectives of the SFD tests are to obtain the data necessary to understand fuel behavior, fission product behavior, and hydrogen generation during severe accidents.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5387883
- Report Number(s):
- EGG-M-39386; CONF-870601-23; ON: DE88006718
- Country of Publication:
- United States
- Language:
- English
Similar Records
Release and deposition of volatile fission products during in-pile severe fuel damage tests
Fission product release rates measured during in-pile fuel damage tests
Results from the Power Burst Facility Severe Fuel Damage Test 1-4
Conference
·
Wed Dec 31 23:00:00 EST 1986
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5534858
Fission product release rates measured during in-pile fuel damage tests
Conference
·
Thu Jan 12 23:00:00 EST 1984
·
OSTI ID:6647516
Results from the Power Burst Facility Severe Fuel Damage Test 1-4
Conference
·
Thu Dec 31 23:00:00 EST 1987
·
OSTI ID:6534324
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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
AEROSOLS
ALKALI METAL COMPOUNDS
ALKALI METALS
ALLOYS
CADMIUM
CESIUM
CESIUM COMPOUNDS
CESIUM HYDROXIDES
CESIUM IODIDES
COLLOIDS
COOPERATION
DAMAGE
DATA
DEPOSITS
DISPERSIONS
ELEMENTS
EXPERIMENTAL DATA
FISSION PRODUCT RELEASE
FISSION PRODUCTS
FUEL CANS
FUEL ELEMENTS
HALIDES
HALOGEN COMPOUNDS
HALOGENS
HYDROGEN
HYDROGEN COMPOUNDS
HYDROXIDES
INDIUM
INFORMATION
INORGANIC PHOSPHORS
INTERNATIONAL COOPERATION
IODIDES
IODINE
IODINE COMPOUNDS
ISOTOPES
MATERIALS
METALS
NONMETALS
NUMERICAL DATA
OXYGEN COMPOUNDS
PHOSPHORS
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
SEMIMETALS
SILVER
SOLS
SOURCE TERMS
STEAM
TELLURIUM
TESTING
TIN ALLOYS
TRANSITION ELEMENTS
VERY HIGH TEMPERATURE
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
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
AEROSOLS
ALKALI METAL COMPOUNDS
ALKALI METALS
ALLOYS
CADMIUM
CESIUM
CESIUM COMPOUNDS
CESIUM HYDROXIDES
CESIUM IODIDES
COLLOIDS
COOPERATION
DAMAGE
DATA
DEPOSITS
DISPERSIONS
ELEMENTS
EXPERIMENTAL DATA
FISSION PRODUCT RELEASE
FISSION PRODUCTS
FUEL CANS
FUEL ELEMENTS
HALIDES
HALOGEN COMPOUNDS
HALOGENS
HYDROGEN
HYDROGEN COMPOUNDS
HYDROXIDES
INDIUM
INFORMATION
INORGANIC PHOSPHORS
INTERNATIONAL COOPERATION
IODIDES
IODINE
IODINE COMPOUNDS
ISOTOPES
MATERIALS
METALS
NONMETALS
NUMERICAL DATA
OXYGEN COMPOUNDS
PHOSPHORS
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
SEMIMETALS
SILVER
SOLS
SOURCE TERMS
STEAM
TELLURIUM
TESTING
TIN ALLOYS
TRANSITION ELEMENTS
VERY HIGH TEMPERATURE
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS