# Evaluation of the KN-12 Spent Fuel Transport Cask by Analysis

• Published : 2002.06.01

#### Abstract

The 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.57-1 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 normal transport and hypothetical accident conditions. W.H 14$\times$14, 16$\times$16 and 17$\times$17 fuel assemblies with maximum allowable initial enrichment of 5.0 wt.%, maximum average burn-up of 50,000 MWD/MTU and minimum cooling time of 7 years being used in Korea will be loaded and subsequently 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 attacked 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 3nd fabricated in Korea in accordance with ASME B&PV Code Section 111, Division 3.

#### References

1. US Nuclear Regulatory Commission, Regulatory Guide 7.6, 'Design Criteria for the Structural Analysis of Shipping Cask Containment Vessels' (1978)
2. US Nuclear Regulatory Commission, Regulatory Guide 7.8, 'Load Combinations for the Structural Analysis of Shipping Casks for Radioactive Material' (1989)
3. Americal Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Section HI, Division 3, 'Containment Systems and Transport Packagings for Spent Nuclear Fuel and High Level Radioactive Waste' (1998)
4. American National Standards Institute, 'Special Lifting Devices for Shipping Containers Weighing 10,000Ibs(4,500kg) or More' (1986)
5. US, 10 CFR Part 71, 'Packaging and Transportation of Radioactive Material' (1997)
6. Korea Ministry of Science and Technology, 'Korea Atomic Energy Act' (1999)
7. International Atomic Energy Agency, IAEA Safety Standards Series No.ST-1, 'Regulations for the Safe Transport of Radioactive Material' (1996)