Open AccessReleasable activity and maximum permissible leakage rate within a transport cask of Tehran Research Reactor fuel samples
Author(s) -
Mahdi Rezaeian,
Jamshid Kamali,
Manoochehr Roshanzamir,
A. Moosakhani,
Elghar Noori
Publication year - 2015
Publication title -
nuclear technology and radiation protection
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.31
H-Index - 16
eISSN - 1452-8185
pISSN - 1451-3994
DOI - 10.2298/ntrp1503232r
Subject(s) - cask , nuclear engineering , environmental science , leakage (economics) , leak , waste management , materials science , containment (computer programming) , engineering , computer science , environmental engineering , economics , macroeconomics , programming language
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