Advanced LBB methodology and considerations

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

OSTI ID:489346

Olson, R; Rahman, S; Scott, P ^[1]

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1. Battelle, Columbus, OH (United States); and others

LBB applications have existed in many industries and more recently have been applied in the nuclear industry under limited circumstances. Research over the past 10 years has evolved the technology so that more advanced consideration of LBB can now be given. Some of the advanced considerations for nuclear plants subjected to seismic loading evaluations are summarized in this paper.

• 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: 489346
• Report Number(s): NUREG/CP-0155; CONF-9510432-; ON: TI97004806; TRN: 97:011487
• 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
PIPES
LEAKS
SAFETY ANALYSIS
MECHANICAL PROPERTIES
FLOW RATE
CRACK PROPAGATION
FRACTURE MECHANICS
CALCULATION METHODS