Properties of a radioactive waste pellet package using cement-glass

Journal Article · Thu Oct 31 23:00:00 EST 1991 · Nuclear Technology; (United States)

OSTI ID:5719353

Funabashi, K; Chino, K ^[1]; Kikuchi, M; Horiuchi, S; Tsuchiya, H ^[2]

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1. Hitachi, Ltd., Energy Research Lab., 1168 Moiyama-cho, Hitachi, Ibaraki-ken 316 (JP)
2. Hitachi, Ltd., Hitachi Works 1-1 Saiwai-cho, 3-chome Hitachi, Ibaraki-ken 316 (JP)

This paper reports on radioactive waste slurry generated from nuclear power plants which is dried and compressed into pellets. These pellets are dropped in a polymer-impregnated concrete (PIC) barrier and solidified with cement-glass, which is a mixture of sodium silicate and cement. The mechanical strength of the PIC barrier is about three times higher than that of ordinary portland cement because of added steel fibers. The leaching ration form the package is experimentally studied using {sup 14}C, {sup 60}Ci, {sup 85}Sr, {sup 99}Tc, {sup 125}I, and {sup 134}Cs. Because of the low porosity of the PIC barrier, the leaching rate is controlled and increases in proportion to immersion time. The maximum leaching ratio from a 200-l package is estimated to be 0.004/yr.

• OSTI ID: 5719353
• Journal Information: Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 96:2; ISSN NUTYB; ISSN 0029-5450
• Country of Publication: United States
• Language: English

Related Subjects

052001* -- Nuclear Fuels-- Waste Processing
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
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ALKALI METAL COMPOUNDS
ALKALINE EARTH ISOTOPES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BUILDING MATERIALS
CARBON 14
CARBON ISOTOPES
CEMENTS
COBALT 60
COBALT ISOTOPES
COMPOSITE MATERIALS
CONCRETES
DAYS LIVING RADIOISOTOPES
DISSOLUTION
ELECTRON CAPTURE RADIOISOTOPES
ENVIRONMENTAL TRANSPORT
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
FABRICATION
GLASS
HOURS LIVING RADIOISOTOPES
INTERMEDIATE MASS NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
LEACHING
LIGHT NUCLEI
MANAGEMENT
MASS TRANSFER
MATERIALS
MECHANICAL PROPERTIES
MINUTES LIVING RADIOISOTOPES
MOLDING
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUCLEI
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
OXYGEN COMPOUNDS
PELLETIZING
PERFORMANCE TESTING
PHASE TRANSFORMATIONS
POLYMERS
POWER PLANTS
PROCESSING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
RADIOISOTOPES
RADIONUCLIDE MIGRATION
REINFORCED CONCRETE
REINFORCED MATERIALS
SEPARATION PROCESSES
SILICATES
SILICON COMPOUNDS
SODIUM COMPOUNDS
SODIUM SILICATES
SOLIDIFICATION
STRONTIUM 85
STRONTIUM ISOTOPES
TECHNETIUM 99
TECHNETIUM ISOTOPES
TESTING
THERMAL POWER PLANTS
WASTE FORMS
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
YEARS LIVING RADIOI
YEARS LIVING RADIOISOT
YEARS LIVING RADIOISOTOPES