الفهرس 
AcknowledgmentOnly 14 pages are availabe for public view
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Abstract
One of the important topics in reactor safety study is the dsses,slllent of the radioactive releases to the brenvironment (source term). The generation of radionuclides initiates as fission fragments, then diffuse through cracks in cladding material to the primary coolant. Quantitative evaluation of the nuclides in primary, seccndary activity treatment via radwaste thi s study• concern. An adopted physical model and computer cede (PWR-GALE ) were to uti I i zed mode I ana 1 y ze, and eval uate the releases of radioactive material in gasesous effluents activity of coolants and these onsite systems aretwo main <from pressurized water reactors. <The calculations are based on data generated from operating reactors, field and laboratory tests, and plants .”. specific design considerations incorporated to reduce the quality of radioactive materials that may be release to the environment during normal operation. The adopted mcdel was expanded to deal with accidental releases through proposing two factors; the effectivness ratio, and the accidental release factor.
e possibility of recycling the gaseous wastes,
during the course of an accident was discussed and
eval ua ted. The code was tested successfull y agai n st. data extracted from acual oper~tional experience and some conblusions were presented.