| Title |
Evaluation of the Mechanical Properties of a HT9 Fuel Cladding Tube for a Sodium-cooled Fast Reactor |
| Authors |
김준환(Jun Hwan Kim); 허형민(Hyeong Min Heo); 백종혁(Jong Hyuk Baek); 김성호(Sung Ho Kim) |
| DOI |
https://doi.org/10.3365/KJMM.2013.51.1.025 |
| ISSN |
1738-8228(ISSN), 2288-8241(eISSN) |
| Keywords |
alloys; deformation; mechanical properties; tensile test; HT9 |
| 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. |