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Please use this identifier to cite or link to this item: http://142.54.178.187:9060/xmlui/handle/123456789/1382
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dc.contributor.authorJan, F-
dc.contributor.authorAhmad, S S-
dc.contributor.authorHasany, S M-
dc.contributor.authorAslam, M-
dc.date.accessioned2019-11-15T10:00:00Z-
dc.date.available2019-11-15T10:00:00Z-
dc.date.issued2007-05-25-
dc.identifier.issn27 169-
dc.identifier.urihttp://142.54.178.187:9060/xmlui/handle/123456789/1382-
dc.description.abstractNear-surface or shallow land disposal of radioactive waste has been the primary practice at the Pakistan Institute of Nuclear Science and Technology (PINSTECH). The adopted choice of this mode of disposal has been based on a study of the site and the quality and quantity of waste generated at the 5 MW reactor with HEU fuel. Specific measures regarding the radiation safety of the workers and environmental protection have been adopted. The waste disposal operations are conducted to meet local regulatory requirements, IAEA recommendations and internationally endorsed principles such as ALARA (as low as reasonably achievable—economic, social and other relevant factors being considered). The data obtained through the years of operational and management experience have manifested the robustness of the disposal system and reliability of the disposal criterion, and have also served to further refine the latter. Consequently, confidence in the current shallow-land-burial practices has increased. Radiological safety of these practices has been assessed by addressing different aspects of the safety and disposal system. These parameters, as indices of a non-exclusive and operational safety model, are presented.en_US
dc.language.isoen_USen_US
dc.publisherInstitute of Physics (IOP)en_US
dc.subjectNatural Scienceen_US
dc.subjectsafety assessmenten_US
dc.subjectsurface disposalen_US
dc.subjectradwasteen_US
dc.subjectPINSTECHen_US
dc.titleA practical profile of integrated safety assessment of near-surface disposal of radwaste at PINSTECHen_US
dc.typeArticleen_US
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