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Vol.51, No.1, 25 ~ 32, 2013
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| Title |
| Evaluation of the Mechanical Properties of a HT9 Fuel Cladding Tube for a Sodium-cooled Fast Reactor |
| 김준환 Jun Hwan Kim , 허형민 Hyeong Min Heo , 백종혁 Jong Hyuk Baek , 김성호 Sung Ho Kim |
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| Abstract |
| As part of developing a fuel cladding tube for the Sodium-cooled Fast Reactor (SFR), KAERI has manufactured a ferritic-martensitic cladding tube (12Cr1MoWV, HT9) in cooperation with a domestic steelmaking company. After making a steel ingot, followed by multiple processes of tube reduction and subsequent heat treatment, a seamless HT9 tube with a 7.4 mm outer diameter, 0.56 mm thickness and 3000 mm length was manufactured. The objective of this study is to evaluate the out-of pile mechanical properties of the HT9 tube for an assessment of quality inspection as well as validation of its performance. An axial tensile test, a biaxial burst test, and a pressurized creep test of the fuel cladding were carried out at various test temperatures. Finally, the long-term mechanical properties were evaluated, along with the mechanical properties and the mid-term aging data, which showed that microstructural change characterized by the aging mechanism can mainly affect the mechanical roperties of the HT9 cladding tube. |
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| Key Words |
| alloys, deformation, mechanical properties, tensile test, HT9 |
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