Published September 2004
| Version v1
Journal article
Vitrification of HLW generated by a production unit for radiopharmaceuticals using simulated waste solutions
- 1. Jaber Ibn Hayan Research Laboratories, Tehran (Iran, Islamic Republic of)
Description
Durable borosilicate glasses for the immobilizing of radioisotopes from nuclear waste streams generated by a radiopharmaceutical production unit are studied. Different boron frits (glasses) and waste-loaded glasses were prepared under various experimental conditions. The effects of some parameters such as melting temperature, cooling procedure and various raw materials were investigated. The best composition of the frits as well as the best glass/waste ratio was determined to optimize the immobilization process. All experiments were performed in non-active bench scale. (author)
Additional details
Publishing Information
- Journal Title
- Journal of Radioanalytical and Nuclear Chemistry
- Journal Volume
- 261
- Journal Issue
- 3
- Journal Page Range
- p. 619-623
- ISSN
- 0236-5731
- CODEN
- JRNCDM
INIS
- Country of Publication
- Hungary
- Country of Input or Organization
- Hungary
- INIS RN
- 35093200
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- BOROSILICATE GLASS; COOLING; ISOTOPE PRODUCTION; MELTING POINTS; MOLYBDENUM 99; RADIOACTIVE WASTE PROCESSING; RAW MATERIALS; VITRIFICATION
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; DAYS LIVING RADIOISOTOPES; EVEN-ODD NUCLEI; GLASS; INTERMEDIATE MASS NUCLEI; ISOTOPES; MANAGEMENT; MATERIALS; MOLYBDENUM ISOTOPES; NUCLEI; PHYSICAL PROPERTIES; PROCESSING; RADIOACTIVE WASTE MANAGEMENT; RADIOISOTOPES; THERMODYNAMIC PROPERTIES; TRANSITION TEMPERATURE; WASTE MANAGEMENT; WASTE PROCESSING
Optional Information
- Notes
- 14 refs.