Published 1995 | Version v1
Book Metadata-only

Modeling relations between the composition and properties of French light water reactor waste containment glass

Creators

  • 1. Commissariat a l'Energie Atomique, Bagnols-sur-Ceze (France)

Description

Models have been developed to calculate the density, molten-state viscosity and initial corrosion rate according to the chemical composition of glass formulations used to vitrify high-level fission product solutions from reprocessed light water reactor fuel. Developed from other published work, these models have been adapted to allow for the effects of platinoid (Ru, Pd, Rh) inclusions on the molten glass rheology

Additional details

Publishing Information

Publisher
Materials Research Society.
Imprint Place
Pittsburgh, PA (United States)
ISBN
1-55899-253-7
Imprint Title
Scientific basis for nuclear waste management 18. Part 1
Imprint Pagination
787 p.
Series
Materials Research Society symposium proceedings, Volume 353.
Journal Page Range
p. 107-113.

Conference

Title
18. international symposium on the scientific basis for nuclear waste management.
Dates
23-27 Oct 1994.
Place
Kyoto (Japan).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
28004679
Subject category
S36: MATERIALS SCIENCE; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CORROSION; GLASS; HIGH-LEVEL RADIOACTIVE WASTES; MATHEMATICAL MODELS; PALLADIUM; PHYSICAL PROPERTIES; RADIOACTIVE WASTE DISPOSAL; RHODIUM; RUTHENIUM; VITRIFICATION; WASTE FORMS; WATER COOLED REACTORS
Descriptors DEC
CHEMICAL REACTIONS; ELEMENTS; MANAGEMENT; MATERIALS; METALS; PLATINUM METALS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; REACTORS; TRANSITION ELEMENTS; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES

Optional Information

Secondary number(s)
CONF-941075--.