Published May 1979 | Version v1
Report Restricted

Leaching of radioactive waste storage glasses

Creators

  • 1. Atomic Energy Research Establishment, Harwell, England

Description

Results are reported of leach tests under various conditions on glass compositions proposed for the vitrification of the highly radioactive waste from the reprocessing of Magnox fuel. Among the variables studies are waste composition, glass devitrification, the source and pH of the water, temperature, and radiation dose to the glass

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Additional details

Publishing Information

Imprint Title
Ceramics in nuclear waste management
Journal Page Range
p. 248-255.
Report number
CONF-790420--

Conference

Title
International symposium on ceramics in nuclear waste management.
Dates
30 Apr - 2 May 1979.
Place
Cincinnati, OH, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
11518457
Subject category
S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CHEMICAL COMPOSITION; CRYSTALLIZATION; GLASS; LEACHING; PH VALUE; PLUTONIUM; RADIATION DOSES; RADIOACTIVE WASTES; TEMPERATURE DEPENDENCE; WATER
Descriptors DEC
ACTINIDES; DISSOLUTION; ELEMENTS; HYDROGEN COMPOUNDS; METALS; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; RADIOACTIVE MATERIALS; SEPARATION PROCESSES; TRANSURANIUM ELEMENTS; WASTES