Published 1973
| Version v1
Report
Effects of Hydrogen content, temperature and crack configuration on fatigue crack propagation and unstable fracture behaviour of Zr-2.5Nb pressure tube
- 1. Hitachi Ltd., Ibaraki (Japan). Hitachi Research Lab.
- 2. Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)
- 3. Tokyo Univ. (Japan). Faculty of Engineering
Description
no abstract available
Availability note (English)
MF available from INIS under the Report Number.Additional details
Publishing Information
- Imprint Pagination
- F 2/3, 12 p.
- Report number
- INIS-mf--963
Conference
- Title
- 2. international conference on structural mechanics in reactor technology.
- Dates
- 10 Sep 1973.
- Place
- Berlin, F.R. Germany.
INIS
- Country of Publication
- European Commission (EC), Brussels (Belgium)
- Country of Input or Organization
- European Commission (EC), Brussels (Belgium)
- INIS RN
- 5115265
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENDING; CRACKS; FATIGUE; FRACTURE PROPERTIES; HYDROGEN; JATR REACTOR; MEETINGS; NIOBIUM ALLOYS; PRESSURE TUBES; QUANTITY RATIO; TEMPERATURE DEPENDENCE; ZIRCONIUM BASE ALLOYS
- Descriptors DEC
- ALLOYS; ELEMENTS; HEAVY WATER MODERATED REACTORS; HWLWR TYPE REACTORS; MECHANICAL PROPERTIES; NATURAL URANIUM REACTORS; NONMETALS; PLUTONIUM REACTORS; POWER REACTORS; REACTORS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; ZIRCONIUM ALLOYS
Optional Information
- Notes
- 18 figs.