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J Radiat Prot > Volume 28(4); 2003 > Article
Journal of Radiation Protection 2003;28(4):291-0.
Containment Evaluation of the KN-12 Transport Cask
Chung, Sung-Hwan;Choi, Byung-Il;Lee, Heung-Young;Song, Myung-Jae;
ABSTRACT
The KN-12 transport cask has been designed to transport 12 PWR spent nuclear fuel assemblies and to comply with the regulatory requirements for a Type B(U) package. The containment boundary of the cask is defined by a cask body, a cask lid, lid bolts with nuts, O-ring seals and a bolted closure lid. The containment vessel for the cask consists of a forged thick-walled carbon steel cylindrical body with an integrally-welded carbon steel bottom and is closed by a lid made of stainless steel, which is fastened to the cask body by lid bolts with nuts and sealed by double elastomer O-rings. In the cask lid an opening is closed by a plug with an O-ring seal and covered by the bolted closure lid sealed with an O-ring. The cask must maintain a radioactivity release rate of not more than the regulatory limit for normal transport conditions and for hypothetical accident conditions, as required by the related regulations. The containment requirements of the cask are satisfied by maintaining a maximum air reference leak rate of $2.7{times}10^{-4}ref.cm^3s^{-1}$ or a helium leak rate of $3.3{times}10^{-4}cm^3s^{-1}$ for normal transport conditions and for hypothetical accident conditions.
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Thermal Evaluation of the KN-12 Transport Cask  2003 ;28(4)
Safety Evaluation of a Radioisotope Transport Package  1997 ;22(4)
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