Published October 1998 | Version v1
Journal article

Cr-Ni alloys for fusion reactors

  • 1. Vserossijskij Nauchno-Issledovatel'skij Inst. Neorganicheskikh Materialov, Moscow (Russian Federation)
  • 2. Sverdlovsk Branch of NIKIET, Zarechny (Russian Federation)
  • 3. A.F. Loffe Inst. of Russian Academy of Sciences, St.-Petersburg (Russian Federation)

Description

Results of comparative study on the physical and mechanical properties, radiation and corrosion resistance of XHM-1 chromium-enriched alloy (44% Cr, Ni-base, 1-2% Mo. Registered name ''Bochvalloy'') and stainless steels (00Cr16Ni15Mo3Nb, 06Cr18Ni10Ti) in the water coolant at temperature up to 350 C have been presented. The XHM-1 alloy is absolutely stable against corrosion cracking, which differs from the behavior of the stainless steels listed. Under tensile stress reaching the yield strength of the material, no corrosion-induced damage of the alloy has occurred in water with various chloride and oxygen contents at a temperature in the range of 50-350 C. In most of the cases, both change of the mechanical strength and relative elongation is not observed after irradiation of the alloy with a dose up to 32 dpa at a temperature of 350 C, which is another distinctive feature of the alloy, as compared to the steels. Concerning totality of the properties, the XHM-1 alloy is very promising material for water cooled fusion reactor components. (orig.)

Additional details

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
258-263
Journal Issue
pt.B
Journal Page Range
p. 1762-1766
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
8. international conference on fusion reactor materials (ICFRM-8)
Dates
26-31 Oct 1997
Place
Sendai (Japan)

Optional Information

Notes
6 refs.