Published 1972 | Version v1
Report

Low-cycle fatigue strength of nozzle-end weldments for reactor pressure vessel

  • 1. Hitachi Ltd., Ibaraki (Japan). Hitachi Research Lab.

Description

no abstract available

Additional details

Publishing Information

Imprint Title
Proceedings of the first international conference on structural mechanics in reactor technology
Imprint Pagination
v. 6 (pt.L) p. 473-487.
Report number
EUR--4820(vol.6)(pt.L)

Conference

Title
First international conference on structural mechanics in reactor technology.
Dates
20 Sep 1971.
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
4064223
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTROL ROD DRIVES; CRACKS; FATIGUE; INCONEL ALLOYS; MEETINGS; NOZZLES; PRESSURE VESSELS; SLEEVES; STAINLESS STEELS; TEMPERATURE DEPENDENCE; THERMAL CYCLING; THREE-DIMENSIONAL CALCULATIONS; TUBES; TWO-DIMENSIONAL CALCULATIONS; WELDED JOINTS
Descriptors DEC
ALLOYS; CHROMIUM ALLOYS; CONTAINERS; IRON ALLOYS; JOINTS; MECHANICAL PROPERTIES; NICKEL ALLOYS; NICKEL BASE ALLOYS; REACTOR COMPONENTS; STEELS

Optional Information

Notes
15 figs.