Published January 1987
| Version v1
Journal article
Thermal behaviour of vitrified high level radioactive waste
- 1. Universidad Complutense de Madrid (Spain). Facultad de Ciencias Quimicas
Description
A thermal model for explaining and simulating temperature distributions in glass solidified radioactive waste is proposed. Four operations of waste management have been considered: a) Cooling of a cylindrical matrix with current air. b) Cooling of a cylindrical matrix under water. c) Cooling of a buried cylindrical matrix in a geological repository (granite). d) Cooling of several arrangements of matrices in a geological repository (granite). (Auth.)
Additional details
Publishing Information
- Journal Title
- Radioact. Waste Manage. Nucl. Fuel Cycle
- Journal Volume
- 8
- Journal Issue
- 1
- Series
- Radioact. Waste Manage. Nucl. Fuel Cycle.
- Journal Page Range
- 23-52
- ISSN
- 0142-2405
- CODEN
- RWMAD
INIS
- Country of Publication
- Switzerland
- Country of Input or Organization
- Switzerland
- INIS RN
- 18055801
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- CONTINUITY EQUATIONS; COOLING; GLASS; HEAT TRANSFER; HIGH TEMPERATURE; HIGH-LEVEL RADIOACTIVE WASTES; MATHEMATICAL MODELS; MEDIUM TEMPERATURE; RADIOACTIVE WASTE PROCESSING; SOLIDIFICATION; TEMPERATURE DISTRIBUTION; TEMPERATURE GRADIENTS; THEORETICAL DATA; VITRIFICATION
- Descriptors DEC
- DATA; DIFFERENTIAL EQUATIONS; ENERGY TRANSFER; EQUATIONS; INFORMATION; MANAGEMENT; MATERIALS; NUMERICAL DATA; PARTIAL DIFFERENTIAL EQUATIONS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; WASTE MANAGEMENT; WASTE PROCESSING; WASTES