Gamma-ray emission tomography examination of TMI-2 core samples
Conference
·
OSTI ID:7170133
An examination method developed at the Idaho National Engineering Laboratory (INEL) is being used to determine the distribution of gamma-ray emitting radionuclides in samples in reactor fuel and prior molten materials. This paper presents the results of a gamma-ray emission tomographic examination performed on cross sections of samples of prior molten fuel material recovered from the TMI-2 reactor. The results indicate substantial relocation of fission products in the debris and the probable accumulation of specific radioactive species in various phases of the material. The observed behavior correlated with the results of microstructural examinations and elemental compositions obtained from SEM/WDX, electron microprobe, and radiochemical analyses. 5 refs., 9 figs.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 7170133
- Report Number(s):
- EGG-M-88172; CONF-881024--23; ON: DE90006948
- Country of Publication:
- United States
- Language:
- English
Similar Records
Gamma-ray emission tomographic examinations of TMI-2 fuel debris
TMI-2 lower vessel debris examinations
Examination of relocated fuel debris adjacent to the lower head of the TMI-2 reactor vessel
Conference
·
Thu Dec 31 23:00:00 EST 1987
·
OSTI ID:7270648
TMI-2 lower vessel debris examinations
Conference
·
Sun Nov 16 23:00:00 EST 1986
·
OSTI ID:6839254
Examination of relocated fuel debris adjacent to the lower head of the TMI-2 reactor vessel
Technical Report
·
Mon Feb 28 23:00:00 EST 1994
·
OSTI ID:10140801
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
42 ENGINEERING
420500 -- Engineering-- Materials Testing
CHEMICAL ANALYSIS
COMPARATIVE EVALUATIONS
CORIUM
COST
COUNTING TECHNIQUES
CRACKS
DATA PROCESSING
DIAGNOSTIC TECHNIQUES
ENRICHED URANIUM REACTORS
ENVIRONMENTAL TRANSPORT
FISSION PRODUCTS
FRAGMENTATION
FUEL ELEMENTS
GAMMA SPECTROSCOPY
ISOTOPES
MASS TRANSFER
MATERIALS
MATERIALS TESTING
MEASURING INSTRUMENTS
MEASURING METHODS
PARTICLES
PARTICULATES
PHOTOGRAPHY
POROSITY
POWER REACTORS
PROBES
PROCESSING
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
RADIONUCLIDE MIGRATION
REACTOR COMPONENTS
REACTOR CORES
REACTORS
REMOTE SENSING
SAMPLING
SPECTROSCOPY
STRUCTURAL MODELS
TESTING
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
TOMOGRAPHY
VERY HIGH TEMPERATURE
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
42 ENGINEERING
420500 -- Engineering-- Materials Testing
CHEMICAL ANALYSIS
COMPARATIVE EVALUATIONS
CORIUM
COST
COUNTING TECHNIQUES
CRACKS
DATA PROCESSING
DIAGNOSTIC TECHNIQUES
ENRICHED URANIUM REACTORS
ENVIRONMENTAL TRANSPORT
FISSION PRODUCTS
FRAGMENTATION
FUEL ELEMENTS
GAMMA SPECTROSCOPY
ISOTOPES
MASS TRANSFER
MATERIALS
MATERIALS TESTING
MEASURING INSTRUMENTS
MEASURING METHODS
PARTICLES
PARTICULATES
PHOTOGRAPHY
POROSITY
POWER REACTORS
PROBES
PROCESSING
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
RADIONUCLIDE MIGRATION
REACTOR COMPONENTS
REACTOR CORES
REACTORS
REMOTE SENSING
SAMPLING
SPECTROSCOPY
STRUCTURAL MODELS
TESTING
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
TOMOGRAPHY
VERY HIGH TEMPERATURE
WATER COOLED REACTORS
WATER MODERATED REACTORS