Formation of Serrated Grain Boundaries and Its Effect on Tensile Properties at 950 ℃ in Alloy 617 for Very High Temperature Reactor
- 1. Changwon National University, Changwon (Korea, Republic of)
- 2. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
The effects of initial microstructures controlled by thermo-mechanical treatment on tensile properties at 950 ℃ were investigated in Alloy 617. Proprietary direct aging combined with a controlled cooling rate led successfully to the transition of serrated grain boundaries (GBs) with a proportion of over 80%. It was newly found that at an initial stage of the transition, the serrated GBs formed without the presence of carbide or a γ' phase in the solid-solution-strengthened Alloy 617. The serrated GBs with stable planar M23C6 carbides enhanced the uniform elongation while the strength was maintained due to higher resistance to GB cavitation al cracking. The fine intragranular carbides, which precipitated substantially through preliminary 5% cold work treatment, were responsible for the strong hardening effect by inhibiting dislocation movement. Based on the results, we propose the initial microstructure for better tensile properties at 950 ℃.
Additional details
Publishing Information
- Journal Title
- Journal of the Korean Institute of Metals and Materials
- Journal Volume
- 53
- Journal Issue
- 1
- Series
- 29 refs, 10 figs, 1 tab
- Journal Page Range
- p. 1-12
- ISSN
- 1738-8228
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 48067016
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AGING; CONTROL; CRACKING; DISLOCATIONS; ELONGATION; GRAIN BOUNDARIES; HARDENING; MICROSTRUCTURE; TENSILE PROPERTIES; VHTR REACTOR
- Descriptors DEC
- CHEMICAL REACTIONS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; DECOMPOSITION; DEFORMATION; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; LINE DEFECTS; MECHANICAL PROPERTIES; MICROSTRUCTURE; POWER REACTORS; PYROLYSIS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS; THERMOCHEMICAL PROCESSES