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Irradiation test of sup 99 Tc and sup 129 I transmutation in the Fast Flux Test Facility

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:7066948
;  [1];
  1. Westinghouse Hanford Co., Richland, WA (United States)

An attractive option for dealing with the problems of nuclear waste disposal includes reprocessing spent light water reactor fuel to recover and recycle the uranium and plutonium, partitioning key long-lived actinides and fission products, and transmuting recovered and purified very long-lived problem isotopes. Most transmutation studies have dealt with the minor actinides; however, a successful transmutation strategy also must address the long-lived fission products {sup 99}Tc and {sup 129}I. Destruction of {sup 99}Tc and {sup 129}I is accomplished by a single neutron-capture event, followed by very rapid decay to stable {sup 100}Ru and {sup 130}Xe, respectively. The probability of a neutron-capture event is significantly higher in a moderated neutron spectrum than in a fast spectrum. Studies have shown that effective transmutation rates of {sup 99}Tc and {sup 129}I potentially can be achieved in specially designed metal hydride assemblies in fast reactors or advanced accelerator-driven devices. A successful transmutation experiment for the key long-lived fission products {sup 99}Tc and {sup 129}I was performed using a metal-hydride-moderated environment in the radial reflector region of a sodium-cooled fast reactor with reasonably good agreement between measured and calculated transmutation rates. The underprediction of both transmutation rates is likely a result of axial gradients in the low-energy neutron flux over the target regions.

OSTI ID:
7066948
Report Number(s):
CONF-911107--
Journal Information:
Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 64; ISSN TANSA; ISSN 0003-018X
Country of Publication:
United States
Language:
English

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Related Subjects

052000* -- Nuclear Fuels-- Waste Management
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
ALKALI METAL COMPOUNDS
BATTELLE PACIFIC NORTHWEST LABORATORIES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BWR TYPE REACTORS
CAPTURE
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EVEN-EVEN NUCLEI
FAST REACTORS
FFTF REACTOR
FISSION PRODUCTS
FUEL ASSEMBLIES
FUEL CYCLE
FUEL MANAGEMENT
FUELS
HALIDES
HALOGEN COMPOUNDS
HIGH-LEVEL RADIOACTIVE WASTES
HOURS LIVING RADIOISOTOPES
HYDRIDES
HYDROGEN COMPOUNDS
INORGANIC PHOSPHORS
INTERMEDIATE MASS NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
IODIDES
IODINE 129
IODINE COMPOUNDS
IODINE ISOTOPES
IRRADIATION CAPSULES
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
LIQUID METAL COOLED REACTORS
MANAGEMENT
MATERIALS
METALS
MODERATORS
NATIONAL ORGANIZATIONS
NEUTRON REFLECTORS
NEUTRON SPECTRA
NUCLEAR FUELS
NUCLEI
ODD-EVEN NUCLEI
PHOSPHORS
PLUTONIUM RECYCLE
POST-IRRADIATION EXAMINATION
POWER REACTORS
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTES
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR EXPERIMENTAL FACILITIES
REACTOR MATERIALS
REACTOR SHUTDOWN
REACTORS
REPROCESSING
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
RESEARCH REACTORS
RUTHENIUM 100
RUTHENIUM ISOTOPES
SELF-SHIELDING
SEPARATION PROCESSES
SHIELDING
SHUTDOWN
SODIUM COMPOUNDS
SODIUM COOLED REACTORS
SODIUM IODIDES
SPECTRA
SPENT FUELS
STABLE ISOTOPES
TECHNETIUM 99
TECHNETIUM ISOTOPES
TEST REACTORS
THERMAL REACTORS
TRANSITION ELEMENTS
TRANSMUTATION
URANIUM RECYCLE
US DOE
US ERDA
US ORGANIZATIONS
VANADIUM
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS
XENON 130
XENON ISOTOPES
YEARS LIVING RADIOI
YEARS LIVING RADIOISOTOPES