Published June 2021
| Version v1
Journal article
Immobilize CeO2 as simulated nuclear waste in natural magmatic granite. Maximum solid solubility
Creators
- 1. Southwest University of Science and Technology, Mianyang, Sichuan (China). State Key Laboratory of Environmental Friendly Energy Materials
- 2. Southwest University of Science and Technology, Mianyang, Sichuan (China). Fundamental Science On Nuclear Wastes and Environmental Safety Laboratory
- 3. Southwest University of Science and Technology, Mianyang, Sichuan (China). National Co-Innovation Center for Nuclear Waste Disposal and Environmental Safety
- 4. Sichuan Radiation Detection and Protection Institute of Nuclear Industry, Chengdu (China)
- 5. Sichuan University, Chengdu (China). Key Laboratory of Radiation Physics and Technology Ministry of Education Institute of Nuclear Science and Technology
- 6. Ministry of Land and Resources, Shaoguan (China). Guangdong Key Laboratory of Radioactive and Rare Resource Utilization
- 7. Nanjing University of Science and Technology, Nanjing, Jiangsu (China)
- 8. Chinese Academy of Sciences, Hefei (China). CAS Key Laboratory of Photovoltaic and Energy Conservation Materials, Institute of Plasma Physics
- 9. University of Science and Technology of China, Hefei (China)
Description
The radionuclides are extracted from the minerals which make up the rocks. This work takes natural magmatic granite as the matrix and CeO2 as the simulated radioactive waste to explore the maximum solid solubility. After analyzing the phase transition of pure granite with varied temperatures, the solidification was carried out at 1300 ℃. The phase, microstructure, element distribution, hardness and chemical stability of the solidified bodies were studied. The results showed that the maximum solid solubility was up to 8 wt.%. The normal leaching rate of Ce4+ after the first 3 d was about 3.89 × 10-7 g·m-2·d-1. (author)
Additional details
Publishing Information
- Journal Title
- Journal of Radioanalytical and Nuclear Chemistry
- Journal Volume
- 328
- Journal Issue
- 3
- Journal Page Range
- p. 795-803
- ISSN
- 0236-5731
- CODEN
- JRNCDM
INIS
- Country of Publication
- Hungary
- Country of Input or Organization
- Hungary
- INIS RN
- 52058793
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- CERAMIC MELTERS; CERIUM OXIDES; GLASS; GRANITES; RADIOACTIVE WASTES; SOLUBILITY; VITRIFICATION
- Descriptors DEC
- CERIUM COMPOUNDS; CHALCOGENIDES; ELECTRIC FURNACES; FURNACES; IGNEOUS ROCKS; MATERIALS; OXIDES; OXYGEN COMPOUNDS; PLUTONIC ROCKS; RADIOACTIVE MATERIALS; RARE EARTH COMPOUNDS; ROCKS; WASTES
Optional Information
- Notes
- 41 refs.