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).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 19066432
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALLOY-ZR98SN-2; BLISTERS; HYDROGEN; PRECIPITATION; THERMAL DIFFUSION; TIME DEPENDENCE; ZIRCONIUM HYDRIDES
- Descriptors DEC
- ALLOYS; CHROMIUM ADDITIONS; CORROSION RESISTANT ALLOYS; DIFFUSION; ELEMENTS; HEAT RESISTING ALLOYS; HYDRIDES; HYDROGEN COMPOUNDS; IRON ADDITIONS; NICKEL ADDITIONS; NONMETALS; SEPARATION PROCESSES; TIN ALLOYS; TRANSITION ELEMENT COMPOUNDS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS; ZIRCONIUM COMPOUNDS