Published 1978 | Version v1
Miscellaneous

Hydrogen embrittlement of material for reactor pressure vessels

  • 1. Ustav Jaderneho Vyzkumu CSKAE, Rez (Czechoslovakia)

Description

Hydrogen embrittlement was tested in low-alloy Cr-Mo-V steel. Specimens were surface finished and electrolytically charged with hydrogen. Hydrogen was determined by means of a single-purpose EAH 220 analyzer by Balzers. Static tensile tests were used for determining the mechanical properties of the steel hydrogenation. The effect of hydrogen was proven in the tested steel. In tensile specimens with notch, higher sensitivity to contraction within a range of 1 ppm to 2 ppm of hydrogen was shown which was due to the parabolic distribution of stress in the specimens. Jumps around the stress maximum in the stress-elongation working diagram only appeared at high over-saturation above 2 ppm. (M.S.)

Additional details

Additional titles

Original title (Czech)
Prispevek k vodikovemu krehnuti materialu pro reaktorove tlakove nadoby

Publishing Information

Imprint Title
Material and technological aspects of WWER reactors. I
Imprint Pagination
230 p.
Journal Page Range
p. 149-166.

Conference

Title
Material and technological aspects of WWER reactors.
Dates
30 Oct - 1 Nov 1978.
Place
Zelezna Ruda, Czechoslovakia.

Optional Information

Notes
Imprint:Materialove a technologicke otazky jadernych reaktoru VVER. 1.