CASTOR® KN-12 SPENT NUCLEAR FUEL TRANSPORT CASK

Year
2001
Author(s)
Rudolf Diersch - GNB Gesellschaft für Nuklear-Behälter mbH
Heung-Young Lee - Nuclear Environment Technology Institute (NETEC) Korea Hydro and Nuclear Power Co., Ltd. (KHNP)
Sung-Hwan Chung - Nuclear Environment Technology Institute (NETEC) Korea Hydro and Nuclear Power Co., Ltd. (KHNP)
Reiner Laughter - GNB Gesellschaft für Nuklear-Behälter mbH
File Attachment
34289.PDF177.36 KB
Abstract
The CASTOR® KN-12 cask is designed to transport 12 PWR spent nuclear fuels and to comply with the requirements of Korea Atomic Energy Act, IAEA Safety Standards Series No.ST-1 and US 10 CFR Part 71 for a Type B(U)F package. It provides containment, radiation shielding, structural integrity, criticality control and heat removal for the normal transport and the hypothetical accident conditions. W.H 14x14, 16x16 and 17x17 fuel assemblies w ith maximum initial enrichment of 5.0 wt.%, maximum burnup of 50000 MWD/MTU and minimum cooling time of 7 years being used in Korea will be loaded and transported under dry and wet conditions. A forged cylindrical cask body which constitutes the containment vessel is closed by a cask lid. Polyethylene rods for neutron shielding are arranged in two rows of longitudinal bore holes in the cask body wall. A fuel basket to accommodate up to 12 PWR fuel assemblies provides support of the fuels, control of criticality and a path to dissipate heat. Impact limiters to absorb the impact energy under the hypothetical accident conditions are attached at the top and at the bottom side of the cask during transport. Handling weight loaded with water is 74.8 tons and transport weight loaded with water with the impact limiters is 84.3 tons. The cask will be licensed in accordance with Korea Atomic Energy Act and fabricated in accordance with ASME Section III, Division 3.