Vitrifiable concrete for disposal of spent nuclear fuel reprocessing waste at I.N.E.L
Creators
- 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).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27068993
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- 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
- Descriptors DEC
- ALKALI METALS; ALKALINE EARTH METALS; ALUMINIUM COMPOUNDS; BUILDING MATERIALS; CHALCOGENIDES; DATA; DISSOLUTION; ELECTRICAL PROPERTIES; ELEMENTS; FABRICATION; INFORMATION; MANAGEMENT; MATERIALS; MATERIALS WORKING; MECHANICAL PROPERTIES; METALS; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; NUMERICAL DATA; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; PRESSING; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; SEPARATION PROCESSES; SILICON COMPOUNDS; US DOE; US ERDA; US ORGANIZATIONS; WASTE DISPOSAL; WASTE MANAGEMENT; WASTE PROCESSING; WASTES
Optional Information
- Secondary number(s)
- CONF-951155--.