Development of Zr-containing advanced reduced-activation alloy (ARAA) as structural material for fusion reactors
- 1. Nuclear Materials Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
- 2. Nuclear Fusion Engineering Development Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
- 3. National Fusion Research Institute, Daejeon (Korea, Republic of)
- 4. AGH University of Science and Technology, Academic Centre of Materials and Nanotechnology, Kraków (Poland)
Description
Highlights: • Creep and impact resistances of reduced activation ferritic–martensitic steel are enhanced by the addition of Zr. • A 5 ton scale heat of Zr containing RAFM steel, ARAA, has been produced for material property evaluation. • The physical, thermal, magnetic and mechanical properties of ARAA are quite similar to those of Eurofer 97. - Abstract: Korea has developed an advanced reduced-activation alloy (ARAA) as a structural material for helium-cooled ceramic reflector test blanket module (HCCR-TBM) applications. The present paper describes the history of alloy development and the properties of ARAA, which has been produced at a 5 t scale using vacuum induction melting and electro-slag re-melting methods. ARAA is a 9Cr–1.2W based ferritic–martensitic steel with 0.01 wt.% Zr. The mechanical properties, thermal properties and physical and magnetic properties of ARAA show similar temperature dependencies to those observed for Eurofer 97. However, ARAA exhibits a much longer creep–rupture time than conventional RAFM steel, which suggests a positive effect on Zr addition. The enhanced creep strength of ARAA by the addition of Zr is attributed to the reduced temperature-dependence of the yield strength.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2016.02.032Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2016.02.032;
- PII
- S0920-3796(16)30114-4;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 109-111
- Journal Issue
- Part A
- Journal Page Range
- p. 629-633
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 12. international symposium on fusion nuclear technology
- Acronym
- ISFNT-12
- Dates
- 14-18 Sep 2015
- Place
- Jeju Island (Korea, Republic of)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48067795
- Subject category
- S36: MATERIALS SCIENCE; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CERAMICS; CREEP; FERRITIC STEELS; HELIUM; MAGNETIC PROPERTIES; MARTENSITIC STEELS; REPUBLIC OF KOREA; RUPTURES; TEMPERATURE DEPENDENCE; TENSILE PROPERTIES; THERMODYNAMIC PROPERTIES; THERMONUCLEAR REACTORS; YIELD STRENGTH; ZIRCONIUM ADDITIONS
- Descriptors DEC
- ALLOYS; ASIA; CARBON ADDITIONS; DEVELOPING COUNTRIES; ELEMENTS; FAILURES; FLUIDS; GASES; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; NONMETALS; PHYSICAL PROPERTIES; RARE GASES; STEELS; TRANSITION ELEMENT ALLOYS; ZIRCONIUM ALLOYS
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.