M. U. Shareef, M. Tufail, S. H. Hussain, F. Rashid


The nuclear technology has prime importance and backbone for rapid development of medical sciences, industries and in power generation as an alternate source of energy. Despite all these facts there is a major problem which is always associated with nuclear technology, that is, the generation of undesirable radioactive wastes. The radioactive wastes are quite problematic and need major attention for its treatment, conditioning and properly disposal to keep the environmental activities and human ecosystem healthy and safe. There are different large scale methods and processes to treat and dispose off the radioactive wastes. These processes are evaluated and designed by the various world competent and pronounced scientists in the light of rules and safety limits set by IAEA and other regulatory authorities to protect the environment and eventually protect our ecosystem. The research and development work on radioactive waste has been proceeding for the last fifty years but still it is a core issue and a big challenge for the nuclear scientists and radiation workers. In this study a rapid and continuous system for immobilization of nuclear waste into glass matrix by vitrification has been designed. In general treatment methods, Borosilicate glass is preferred because it is efficient, cost effective and rapid to that of other radioactive waste form. In this process the simulated waste is mixed with glass forming material and process for melting to form a glassy substrate in continuous manner. The waste is being converted into vitreous form and encapsulate into a glass matrix

Full Text:



International Atomic Energy Agency, Design

and Operation of Evaporator for Radioactive

Wastes, Technical Report Series No.87

(IAEA, Vienna, 1968).

International Atomic Energy Agency,

Handling and Storage of High Level

Radioactive Liquid Wastes requiring Cooling,

Technical Report Series No.191 (IAEA,

Vienna, 1979).

Ronnie D.Lipschutz,“Radioactive Waste,

Politics, Technology, and Risk”, Ballinger

Publishing Company (Cambridge,

Massachusetts, 1980).

N.E. Brenzenva et al, “Vitrification of high

sodium- aluminum wastes: Composition

ranges and properties, Scientific Basis

International Symposium Boston, 1978,

McCarthy, G.J., Ed., (Plenum Nuclear Waste

Management, New York, (1979) 43-50.

Chang Ho Oh, “Hazardous and Radioactive

Waste Treatment Technologies Handbook”,

CRC (Press, Boca Raton, Florida, USA,


Masumitsu Kubota, “Recovery of Technetium

from high Level Liquid Waste Generated in

Nuclear Fuel Reprocessing” Department of

Chemistry and Fuel Research, Radiochimica

Acta 6.3,91-96 (Japan Atomic Energy

Research institute, April 27,1993 ).


  • There are currently no refbacks.