Published 1996 | Version v1
Book Metadata-only

Fracture mechanics toughness behavior of pressure vessel steels in the ductile-to-brittle transition region: An important issue to nuclear reactor integrity

Creators

  • 1. CTMSP, Sao Paulo (Brazil)
  • 2. IPEN, Sao Paulo (Brazil)
  • 3. CNEA, Buenos Aires (Argentina)
  • 4. Univ. of Tennessee, Knoxville, TN (United States)
  • 5. Oak Ridge National Lab., TN (United States)

Description

ASTM E-08 Committee has been developing a new standard, to deal with the fracture mechanics behavior of steels in the ductile to brittle transition region. This paper presents a comparison between the current approach and a new proposal to be used by the nuclear industry to face the problem of determining the behavior of ferritic steels. An emphasis will be given to the application of this proposal and its evaluation using a Brazilian A508 Class 3 nuclear steel

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (United States)
ISBN
0-7918-1771-7
Imprint Title
Fatigue and fracture -- 1996: Volume 2. PVP-Volume 324
Imprint Pagination
295 p.
Journal Page Range
p. 175-182.

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
28017287
Subject category
S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DATA; FERRITIC STEELS; FRACTURE MECHANICS; LOW ALLOY STEELS; NUCLEAR POWER PLANTS; PRESSURE VESSELS; REACTOR MATERIALS; RELIABILITY; STANDARDS
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CONTAINERS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; STEELS; THERMAL POWER PLANTS; TRANSITION ELEMENT ALLOYS

Optional Information

Secondary number(s)
CONF-960706--.