Published November 1, 2016 | Version v1
Journal article

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.2016.02.032

Additional 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)

Optional Information

Copyright
Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.