Published 1996 | Version v1
Book Metadata-only

The reconstitution of Charpy-size tensile specimens

Creators

  • 1. SCK-CEN, Mol (Belgium)

Description

Charpy-size tensile specimens have been reconstituted starting from broken Charpy specimens. Precautions have been taken to prevent fracture in the weld regions of the reconstituted specimens. Careful qualification of the tensile properties of the reconstituted tensile bars has been established and is in agreement with test results on ASTM/E8-size tensile specimens. The tensile properties of the unirradiated weld material of the Belgian PWR Doel 2 and of the unirradiated base metal of the German BWR Philippsburg 1 have been determined using this methodology. Both the resulting yield and maximum loads are in agreement with the actual expectations. Qualification to apply the technique on irradiated specimens is in preparation

Additional details

Publishing Information

Publisher
American Society for Testing and Materials.
Imprint Place
West Conshohocken, PA (United States)
ISBN
0-8031-2016-8
Imprint Title
Effects of radiation on materials: 17. international symposium
Imprint Pagination
[1175 p.].
Series
ASTM special technical publication, 1270.
Journal Page Range
p. 442-457.
ISSN
1050-7515

Conference

Title
17. symposium on effects of radiation on materials.
Dates
20-23 Jun 1994.
Place
Sun Valley, ID (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
28075961
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CHARPY TEST; DOEL-2 REACTOR; PHILIPPSBURG-1 REACTOR; REACTOR MATERIALS; SAMPLE PREPARATION; TENSILE PROPERTIES; WELDED JOINTS
Descriptors DEC
BWR TYPE REACTORS; DESTRUCTIVE TESTING; ENRICHED URANIUM REACTORS; IMPACT TESTS; JOINTS; MATERIALS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-940657--.