Published March 1985
| Version v1
Journal article
Effect of oxygen content on tensile properties of low oxygen Zircaloy-2
- 1. Nippon Nuclear Fuel Development Co. Ltd., Oarai, Ibaraki
Description
no abstract available
Additional details
Publishing Information
- Journal Title
- J. Nucl. Sci. Technol. (Tokyo)
- Journal Volume
- 22
- Journal Issue
- 3
- Series
- J. Nucl. Sci. Technol. (Tokyo).
- Journal Page Range
- 239-241
- ISSN
- 0022-3131
- CODEN
- JNSTA
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 17005991
- Subject category
- S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- No Abstract
- Descriptors DEI
- ALLOY-ZR98SN-2; BWR TYPE REACTORS; CORROSION RESISTANCE; FUEL CANS; HEAT TREATMENTS; HIGH TEMPERATURE; OXYGEN; TENSILE PROPERTIES; VICKERS HARDNESS
- Descriptors DEC
- ALLOYS; CHROMIUM ADDITIONS; CORROSION RESISTANT ALLOYS; ELEMENTS; ENRICHED URANIUM REACTORS; HEAT RESISTING ALLOYS; IRON ADDITIONS; MECHANICAL PROPERTIES; NICKEL ADDITIONS; NONMETALS; POWER REACTORS; REACTORS; THERMAL REACTORS; TIN ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- Published in summary form only.