11–15 Sept 2017
Congress Graz, Austria
UTC timezone

Development of material manufacturing technology and welding rods for spent nuclear fuel shipping cask

11 Sept 2017, 16:10
20m
Room A (Congress Graz, Austria)

Room A

Congress Graz, Austria

Albrechtgasse 1 8010 Graz Austria
Oral Presentation Advanced and new forging materials Advanced and new forging materials

Speaker

Mr Kuk-Cheol Kim (Doosan Heavy Industries & Construction)

Description

The objective of this study is to develop the spent nuclear fuel shipping cask shell material and welding rods with high toughness at very low temperature. Recently, in Korea, The demand of shipping cask has been increased to transfer spent nuclear fuel and nuclear waste to an interim facility and store safely due to the limitation of the storage space inside nuclear power plant. The shipping cask is required to have excellent toughness for ensuring structural integrity even against hypothetical free dropping accident during transportation. In particular, in Korea, the shipping cask shell material and its weldment should be satisfied with the strict additional design requirement of Reference Temperature for Nil-Ductility Transition (RTNDT) of colder than -105oC to verify safety even in very low temperature environment. For SA350 LF3 low alloy steel using several small blocks, optimum alloy design has been performed through the optimization of chemical compositions such as C, Al and addition of boron. Also, optimum heat treatment process has been set up to get fine ferrite and austenite microstructure for improving toughness. Through the manufacture of the 30 ton cask shell forging with diameter of 1,900mm and wall thickness of 540mm, we can confirm that the cask material have excellent toughness satisfied with material specification of SA350 LF3 and RTNDT design requirement. Also, welding rods satisfied with RTNDT criteria of -105oC for GTAW, GMAW and SAW process have successfully developed through the alloy design and optimum welding heat input. Through this research, we can obtain the manufacturing technology of spent nuclear fuel shipping cask for Korean nuclear industry.

Author

Mr Kuk-Cheol Kim (Doosan Heavy Industries & Construction)

Co-authors

Dr Byoung-Koo Kim (Doosan Heavy Industries & Construction) Mr Jae-Hyung Lee (Doosan Heavy Industries & Construction) Dr Jae-Suk Jeong (Doosan Heavy Industries & Construction) Mr Jae-Woong Lee (Doosan Heavy Industries & Construction) Mr Sang-Dong Lee (Doosan Heavy Industries & Construction) Mr Tae-Hoon Noh (KISWEL)

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