Vitrifiable concrete for disposal of spent nuclear fuel reprocessing waste at I.N.E.L.

Book · Thu Aug 01 04:00:00 EDT 1996

OSTI ID:264445

Gougar, M L.D.; Scheetz, B E ^[1]; Siemer, D D ^[2]

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1. Pennsylvania State Univ., University Park, PA (United States). Materials Research Lab.
2. Lockheed International Technologies Co., Idaho Falls, ID (United States). Idaho National Engineering Labs.

A cement capable of being Hot Isostatically Pressed (HIP`ed) into a glass-ceramic has been proposed for use as the waste form for SNF reprocessing wastes at the Idaho National Engineering Laboratories. Such an ``intermediate`` cement, with a composition based on that of common glasses, has been designed and tested. The cement formulations included mixed I.N.E.L. wastes, blast furnace flag, reactive silica, alumina, and I.N.E.L. soil or vermiculite, which was activated with potassium or sodium hydroxide. Modified FUETAP processing was performed and the cement was subsequently characterized. Results of compressive strength testing ranged from 1,452 psi to 4,163 psi, exceeding the NRC-suggested standard of >500 psi. Total dissolved solids concentrations in waste form leachates were calculated from a static leach test in which leachate conductivity was measured. Effective diffusivities for radioisotopes Cs and Sr were calculated from leachate analysis data. Diffusivity values were on the order of 10{sup {minus}15} to 10{sup {minus}10} cm{sup 2}/sec, which compare favorably with diffusivities in other materials.

• OSTI ID: 264445
• Report Number(s): CONF-951155--; ISBN 1-55899-315-0
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
ALUMINIUM OXIDES
CEMENTS
CESIUM
CHEMICAL COMPOSITION
COMPRESSION STRENGTH
DIFFUSION
ELECTRIC CONDUCTIVITY
EXPERIMENTAL DATA
FUEL REPROCESSING PLANTS
HIGH-LEVEL RADIOACTIVE WASTES
HOT PRESSING
IDAHO NATIONAL ENGINEERING LABORATORY
LEACHING
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE PROCESSING
SILICON OXIDES
SLAGS
SOILS
STRONTIUM
WASTE FORMS