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.