Hot crack susceptibility in multi-pass welds of reduced activation ferritic/martensitic steel F82H
Source abstract
Abstract
Abstract The research and development of nuclear fusion reactors are going on conducting to acquire a next-generation energy source. It is supposed to be that the reduced activation ferritic/martensitic (RAFM) steel F82H is adopted as a structural material of the blanket module, which is the device set on the inner wall of fusion reactors. As welding for thicker plates of F82H, multi-pass welding will be adopted to the joints. In the case of multi-pass welding, hot cracking is one of serious defects in welds and is concerned in welds reheated by following weld passes. Therefore, the objectives of this study are to evaluate hot crack susceptibility in multi-pass welds of F82H and to clarify the cause of hot cracking in multi-pass welds of F82H. The hot crack susceptibility in multi-pass welds is evaluated by the longitudinal Varestraint test with double-bead and triple-bead types. From the observation of fractured surface occurred in welds of F82H after the Varestraitnt test, the crack is identified as ductility-dip crack. The cause of hot crack in multi-pass welds of F82H is clarified by Vickers hardness test, SEM microstructure observations and X-ray diffraction pattern analyses. Based on these tests, when multi-pass welding is conducted for the F82H steels with high Ta contents, it should be considered to control welding conditions for prevention of hot cracking in weld metal as well as high strength martensitic steels. These results suggest that the cause of the crack is intragranular hardening by the precipitation of TaN during welding thermal cycles.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (15)
Show source-provided references
1. Report of the International Symposium for ITER · 2002
2. Breeding blanket modules testing in ITER10.1016/j.fusengdes.2005.08.096 ↗
3. Development of potential low activation ferritic and austenitic steels10.1016/0022-3115(86)90144-3 ↗
4. Effects of neutron irradiation on the tensile properties of high-Croxide dispersion strengthened ferritic steels10.1016/j.jnucmat.2007.03.140 ↗
5. Irradiation creep and microstructural changes in an advanced ODS ferritic steel during helium implantation under stress10.1016/j.jnucmat.2008.12.081 ↗
6. Effect of heat treatment process for blanket fabrication on mechanical properties of F82H10.1016/j.jnucmat.2004.04.047 ↗
7. Production of low activation steel JLF-1, large heats -Current status and future plan-10.1016/S0022-3115(98)00198-6 ↗
8. Vanadium alloys for fusion blanket. Applications10.2320/matertrans.46.405 ↗
9. Current status and future R&D for reduced-activation ferritic/martensitic steels10.1016/S0022-3115(98)00395-X ↗
10. The ITER blanket and divertor sections procuring domestic agencies, blanket integrated product team “engineering challenges and development of the ITER blanket system and divertor”10.1016/j.fusengdes.2015.06.045 ↗
11. Böllinghaus · 2008
12. Hot cracking susceptibility of F82H with controlled Ta content10.1016/j.jnucmat.2011.01.056 ↗
13. Development of an extensive database of mechanical and physical properties for reduced-activation martensitic steel F82H
14. Prediction of welding residual stress in multi-pass butt-welded modified 9Cr–1Mo steel pipe considering phase transformation effects10.1016/j.commatsci.2005.06.010 ↗
15. Present development status of EUROFER and ODS-EUROFER for application in blanket concepts