Published 1992 | Version v1
Book Metadata-only

Stable crack growth phenomena of welded CT specimens and their simplified assessment

Creators

  • 1. Univ. of Tokyo (Japan). Dept. of Nuclear Engineering
  • 2. Central Research Inst. of Electric Power Industry, Tokyo (Japan)
  • 3. Kawasaki Heavy Industries, Ltd., Tokyo (Japan)

Description

This paper describes numerical studies and simplified assessment of stable crack growth phenomena in welded CT specimens made of a nuclear pressure vessel A533B class 1 steel. The orientation of a cracks in the specimens is normal to the phase boundary between base metal and weld metal. At first, elastic-plastic finite element analyses of stationary cracks in the welded CT specimens were per-formed by parametrically varying the material properties of the weld metal and the distance between the crack-tip and the phase boundary. The influences of these factors to the J-integral evaluations were examined in detail. Next, the crack growth simulations based on the elastic-plastic finite element method and the GE/EPRI method were performed for welded CT specimens with three different crack-tip locations. The comparison among the experimental, numerical and simplified assessment results showed that the finite element crack growth analyses simulate well crack growth phenomena in the welded CT specimens, but that the GE/ EPRI method needs some modification of material properties to estimate these phenomena

Part of:
Pressure vessel fracture, fatigue, and life management: PVP-Volume 233

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (United States)
ISBN
0-7918-0774-6
Imprint Title
Pressure vessel fracture, fatigue, and life management: PVP-Volume 233
Imprint Pagination
312 p.
Journal Page Range
p. 181-186.

Conference

Title
American Society of Mechanical Engineers (ASME) pressure vessels and piping conference.
Dates
21-25 Jun 1992.
Place
New Orleans, LA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
25058446
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
COMPARATIVE EVALUATIONS; CRACK PROPAGATION; EXPERIMENTAL DATA; FRACTURE MECHANICS; PARAMETRIC ANALYSIS; PRESSURE VESSELS; REACTORS; STEEL-MNNIMO; THEORETICAL DATA; WELDED JOINTS
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CONTAINERS; DATA; EVALUATION; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; LOW ALLOY STEELS; MANGANESE ALLOYS; MECHANICS; MOLYBDENUM ADDITIONS; NICKEL ADDITIONS; NUMERICAL DATA; STEELS

Optional Information

Secondary number(s)
CONF-920631--.