The nature thickness pipe element testing method to validate the application of LBB conception

Conference · Tue Apr 01 00:00:00 EST 1997

OSTI ID:489335

Vasilchenko, G S; Artemyev, V I; Merinov, G N ^[1]

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1. and others

To validate the application of leak before break analysis to the VVER-1000 reactor, a procedure for testing a large-scale specimen on electrohydraulic machinery was developed. Steel pipe with a circular weld and stainless cladding inside was manufactured and large-scale longitudinal cross-sections were cut. The remaining parts of the weld after cut out were used to determination standard tensile mechanical properties, critical temperature of brittlness and for manufacture of compact specimens. Experimental mechanical properties of the weld are summarized.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering Technology; Electricite de France (EDF), 69 - Villeurbanne (France); Battelle Memorial Inst., Columbus, OH (United States)
• OSTI ID: 489335
• Report Number(s): NUREG/CP-0155; CONF-9510432-; ON: TI97004806; TRN: 97:011475
• Resource Relation: Conference: Seminar on leak before break in reactor piping and vessels, Lyon (France), 9-11 Oct 1995; Other Information: PBD: Apr 1997; Related Information: Is Part Of Proceedings of the seminar on leak before break in reactor piping and vessels; Faidy, C. [ed.] [Electricite de France, Villeurbanne (France)]; Gilles, P. [ed.] [Framatome, Paris (France)]; PB: 773 p.
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
PIPES
LEAKS
STAINLESS STEELS
FRACTURE PROPERTIES
WELDED JOINTS
WWER-5 REACTOR
BENCH-SCALE EXPERIMENTS
YIELD STRENGTH
ULTIMATE STRENGTH
ELONGATION
STRAIN RATE