Published July 1985 | Version v1
Journal article

Formation of hydride blisters in zirconium alloy pressure tubes

Creators

  • 1. Atomic Energy of Canada Ltd., Pinawa, Manitoba. Whiteshell Nuclear Research Establishment

Description

The fracture of the Zircaloy-2 pressure tube in the Pickering Unit 2 power reactor was associated with the growth of hydride blisters at points of contact between the pressure tube and the cooler calandria tube surrounding it. Similar blisters have been observed in a Zr-2.5 wt% Nb pressure tube in WR-1, an organic-cooled research reactor. These hydride blisters were formed and grew as a result of the thermal diffusion of hydrogen in the zirconium, a mechanism whereby hydrogen diffuses down a temperature gradient. If the terminal solid solubility of hydrogen is exceeded in the cooler regions, hydride will precipitate. In this paper, the time required to grow these hydride blisters will be estimated from the blister size and the hydrogen distribution in its neighborhood, by using simple equations derived from thermal diffusion theory

Additional details

Publishing Information

Journal Title
Can. Metall. Q.
Journal Volume
24
Journal Issue
3
Series
Can. Metall. Q.
Journal Page Range
227-234
ISSN
0008-4433
CODEN
CAMQA

Conference

Title
Symposium on zirconium alloys in service in nuclear reactors.
Dates
1984.
Place
Quebec City (Canada).