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...
Main Authors: | , , , , |
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Format: | Article |
Language: | English |
Published: |
VINCA Institute of Nuclear Sciences
2015-01-01
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Series: | Nuclear Technology and Radiation Protection |
Subjects: | |
Online Access: | http://www.doiserbia.nb.rs/img/doi/1451-3994/2015/1451-39941503232R.pdf |
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. |
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ISSN: | 1451-3994 1452-8185 |