Published December 2012 | Version v1
Journal article Metadata-only

The measurement of the radiolytic gas produced from resin waste solidified in cement

Creators

  • 1. China Institute for Radiation Protection, Taiyuan (China)

Description

Airproof steel container for measurement of radiolytic gas produced from resin waste solidified in cement were manufactured and tested. Waste resin was sealed in container and irradiated by γ-rays at room temperature with 106 Gy. Qualitative and quantitative analysis of gaseous products produced from irradiation were carried out by using gas chromatography. Six kinds of radiolytic gas can be detected and the yield of H2 is 34.77%-49.75%. The radiolytic gas must be concerned when the resin waste or resin waste solidified in cement is stored or treated. (authors)

Additional details

Publishing Information

Journal Title
Journal of Radiation Research and Radiation Processing
Journal Volume
30
Journal Issue
6
Journal Page Range
p. 370-373
ISSN
1000-3436

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
51053386
Subject category
S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S38: RADIATION CHEMISTRY, RADIOCHEMISTRY AND NUCLEAR CHEMISTRY;
Descriptors DEI
CEMENTS; CONTAINERS; GAMMA RADIATION; GAS CHROMATOGRAPHY; HYDROGEN; IRRADIATION; RADIOACTIVE WASTES; RADIOLYSIS; RESINS; SOLIDIFICATION; TEMPERATURE RANGE 0273-0400 K
Descriptors DEC
BUILDING MATERIALS; CHEMICAL RADIATION EFFECTS; CHEMICAL REACTIONS; CHROMATOGRAPHY; DECOMPOSITION; ELECTROMAGNETIC RADIATION; ELEMENTS; IONIZING RADIATIONS; MATERIALS; NONMETALS; ORGANIC COMPOUNDS; ORGANIC POLYMERS; PETROCHEMICALS; PETROLEUM PRODUCTS; PHASE TRANSFORMATIONS; POLYMERS; RADIATION EFFECTS; RADIATIONS; RADIOACTIVE MATERIALS; SEPARATION PROCESSES; TEMPERATURE RANGE; WASTES

Optional Information

Notes
2 figs., 3 tabs., 10 refs.