Published December 1994
| Version v1
Journal article
Development of new zirconium alloys for fuel cans of WWR type reactors
Creators
Description
A consideration is given to the experience of designing and development of zirconium base alloys abroad. Test results are presented for behaviour of fuel cans in WWR type reactors. The problems of corrosion resistance and radiation-induced growth of zirconium alloys are discussed. 16 figs.; 4 tabs
Additional details
Additional titles
- Original title (Russian)
- Разработка новых циркониевых сплавов для оболочек твэлов водо-водяных реакторов
Publishing Information
- Journal Title
- Atomnaya Tekhnika za Rubezhom
- Journal Issue
- no.12
- Journal Page Range
- p. 3-11.
- ISSN
- 0320-9326
- CODEN
- ATRUA8
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Russian Federation
- INIS RN
- 26065744
- Subject category
- S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Descriptors DEI
- BURNUP; CHEMICAL COMPOSITION; CORROSION RESISTANCE; FUEL CANS; NEUTRON FLUENCE; PHYSICAL RADIATION EFFECTS; REVIEWS; TENSILE PROPERTIES; WWR TYPE REACTORS; ZIRCONIUM BASE ALLOYS
- Descriptors DEC
- ALLOYS; DOCUMENT TYPES; ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; RADIATION EFFECTS; REACTORS; TANK TYPE REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS