Published 1996 | Version v1
Book Metadata-only

Effect of long-term thermal aging on the material properties of nickel-base alloy and carbon steel welded joints

Creators

  • 1. Japan Power Engineering and Inspection Corp., Chiba (Japan)
  • 2. Toshiba Corp., Yokohama (Japan)
  • 3. Hitachi Ltd. (Japan)
  • 4. Univ. of Tokyo (Japan)

Description

To extend the LWR plant life, the technical basis is required to evaluate the lives of structural components with the data base of the age-related degraded material properties. In BWR plants, CRD stub tubes of RPV, and core-internals, etc. are mainly fabricated from nickel-base alloy and austenitic stainless steel, and nozzle safe-ends of RPV and reactor coolant pressure boundary piping are mainly fabricated from carbon steels. In order to evaluate the service lives of these components, it is necessary to clarify the fatigue properties and fracture toughness of the long-term thermally aged materials. The present study provides the material test results of thermally aged Alloy 600 (SB166) welded joints and carbon steel (SA508C ell.1) welded joints thermally aged at the aging condition equivalent to 80 year service life. The present paper mainly describes the results of the fatigue strength, fatigue crack growth in the simulated BWR water environment, fracture toughness tests, and Charpy impact test of the thermally aged Alloy 600 (SB166) and carbon steel welded joints

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (United States)
ISBN
0-7918-1782-2
Imprint Title
Service experience and design in pressure vessels and piping (including high pressure technology). PVP-Volume 335
Imprint Pagination
267 p.
Journal Page Range
p. 13-20.

Conference

Title
American Society of Mechanical Engineers (ASME) pressure vessels and piping conference.
Dates
21-26 Jul 1996.
Place
Montreal (Canada).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
28018863
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
BWR TYPE REACTORS; CRACK PROPAGATION; EXPERIMENTAL DATA; FATIGUE; FRACTURE PROPERTIES; INCONEL 600; REACTOR COMPONENTS; REACTOR MATERIALS; RELIABILITY; SERVICE LIFE; WATER CHEMISTRY; WELDED JOINTS
Descriptors DEC
ALLOY-NI76CR15FE8; ALLOYS; ALUMINIUM ADDITIONS; CHEMISTRY; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DATA; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INCONEL ALLOYS; INFORMATION; IRON ALLOYS; JOINTS; LIFETIME; MATERIALS; MECHANICAL PROPERTIES; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; NUMERICAL DATA; POWER REACTORS; REACTORS; THERMAL REACTORS; TITANIUM ADDITIONS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-960706--.