Interim Storage of Solidified High Level Wastes

by P. D. Ozarde, Bhabha Atomic Research Cent, Bombay, India,
D. S. Rana, Bhabha Atomic Research Cent, Bombay, India,
S. D. Misra, Bhabha Atomic Research Cent, Bombay, India,
M. S. Kumra, Bhabha Atomic Research Cent, Bombay, India,



Document Type: Proceeding Paper

Part of: High Level Radioactive Waste Management 1991

Abstract: Indian approach to the problem of interim storage of vitrified high level wastes, indicating design philosophy adopted for air cooled vault at Tarapur has been described. Important design parameters, analysed in this paper, are optimisation of storage unit geometry, vault design, array design, storage unit filling / loading patterns, activity, temperature profiles etc. Analysis of the abnormal and accidental conditions are followed by risk analysis studies for such a storage concept.

Subject Headings: Waste storage | Risk management | Solid wastes | Radioactive wastes | Thermal analysis | Solidification | Air temperature | Temperature distribution

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