Instability predictions for circumferentially cracked Type-304 stainless-steel pipes under dynamic loading. Final report. [BWR]

Technical Report · Thu Apr 01 00:00:00 EST 1982

OSTI ID:5293766

Zahoor, A; Wilkowski, G; Abou-Sayed, I; Marschall, C; Broek, D; Sampath, S; Rhee, H; Ahmad, J

This report provides methods to predict margins of safety for circumferentially cracked Type 304 stainless steel pipes subjected to applied bending loads. An integrated combination of experimentation and analysis research was pursued. Two types of experiments were performed: (1) laboratory-scale tests on center-cracked panels and bend specimens to establish the basic mechanical and fracture properties of Type 304 stainless steel, and (2) full-scale pipe fracture tests under quasi-static and dynamic loadings to assess the analysis procedures. Analyses were based upon the simple plastic collapse criterion, a J-estimation procedure, and elastic-plastic large-deformation finite element models.

• Research Organization: Battelle Columbus Labs., OH (USA)
• OSTI ID: 5293766
• Report Number(s): EPRI-NP-2347-Vol.1; ON: DE82903281; TRN: 82-013207
• Resource Relation: Other Information: Portions of document are illegible
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
BWR TYPE REACTORS
PIPES
CRACKS
DYNAMIC LOADS
STAINLESS STEEL-304
FRACTURE PROPERTIES
STRESS CORROSION
REACTOR MATERIALS
STRESS ANALYSIS
ALLOYS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION
CORROSION RESISTANT ALLOYS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
NICKEL ALLOYS
REACTORS
STAINLESS STEELS
STEELS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
360105 - Metals & Alloys- Corrosion & Erosion
360103 - Metals & Alloys- Mechanical Properties