Published 1996 | Version v1
Book

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

  • 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.

Description

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 10-15 to 10-10 cm2/sec, which compare favorably with diffusivities in other materials

Additional details

Publishing Information

Publisher
Materials Research Society.
Imprint Place
Pittsburgh, PA (United States)
ISBN
1-55899-315-0
Imprint Title
Scientific basis for nuclear waste management 19
Imprint Pagination
957 p.
Series
Materials Research Society symposium proceedings, Volume 412.
Journal Page Range
p. 395-402.

Conference

Title
Fall meeting of the Materials Research Society (MRS).
Dates
27 Nov - 1 Dec 1995.
Place
Boston, MA (United States).

Optional Information

Secondary number(s)
CONF-951155--.