Releasable activity and maximum permissible leakage rate within a transport cask of Tehran Research Reactor fuel samples

Containment of a transport cask during both normal and accident conditions is important to the health and safety of the public and of the operators. Based on IAEA regulations, releasable activity and maximum permissible volumetric leakage rate within the cask containing fuel samples of Tehr...

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Bibliographic Details
Main Authors: Rezaeian Mahdi, Kamali Jamshid, Roshanzamir Manoochehr, Moosakhani Alireza, Noori Elghar
Format: Article
Language:English
Published: VINCA Institute of Nuclear Sciences 2015-01-01
Series:Nuclear Technology and Radiation Protection
Subjects:
Online Access:http://www.doiserbia.nb.rs/img/doi/1451-3994/2015/1451-39941503232R.pdf
Description
Summary:Containment of a transport cask during both normal and accident conditions is important to the health and safety of the public and of the operators. Based on IAEA regulations, releasable activity and maximum permissible volumetric leakage rate within the cask containing fuel samples of Tehran Research Reactor enclosed in an irradiated capsule are calculated. The contributions to the total activity from the four sources of gas, volatile, fines, and corrosion products are treated separately. These calculations are necessary to identify an appropriate leak test that must be performed on the cask and the results can be utilized as the source term for dose evaluation in the safety assessment of the cask.
ISSN:1451-3994
1452-8185