Published July 1991 | Version v1
Journal article

Surface ripple of resolidified stainless steel after disruption load

  • 1. Nuclear Engineering Research Lab., Univ. of Tokyo, Ibaraki (Japan)
  • 2. R and D Labs.-II, Nippon Steel Corp. (Japan)

Description

The lifetime the first wall in fusion reactor depends on its durability against plasma disruption loads that may cause the melting and evaporation of the surface layer. Irradiation tests for stainless steels were made using a neutral beam injector. It was found that high sulfur and oxygen contents in the steels made the resolidification surfaces rough and wavy, while high calcium, aluminum and titanium contents were revealed to effectively offset the sulfur and oxygen. These impurity contents affect the temperature coefficient of surface tension in liquid iron. The surface temperature in the wider sections declines more slowly than in the thinner parts, therefore, the surface temperature is nonuniform. When the liquid iron has a positive temperature coefficient of surface tension, the surface tension in the denser parts becomes relatively greater than in the thinner parts. Consequently, the former expands and the thinner section contracts. (orig.)

Additional details

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
15
Journal Issue
1
Series
Fusion Eng. Des.
Journal Page Range
75-81
ISSN
0920-3796
CODEN
FEDEE

Conference

Title
Japan-United States workshop on the evaluation of graphite as a first wall material and the development of first wall engineering for the next large fusion devices.
Dates
3-4 Feb 1989.
Place
Tokyo (Japan).