Lessons learned from application of the LBB concept to the NPPs with VVER 440 type 213 reactors

Conference · Fri Dec 01 00:00:00 EST 1995

OSTI ID:136776

Pecinka, L; Zdarek, J ^[1]

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1. Nuclear Research Inst., Rez u Prahy (Czech Republic). Division of Integrity and Materials

Based on the high safety significance of the Leak Before Break (LBB) concept for nuclear power plants (NPPS) with Soviet Pressure Water Reactors with electrical power 440 MW denominated as VVER 440 type 230, the International Atomic Energy Agency (IAEA) has decided to pay more attention to this important issue in order to assist countries operating these first generation VVERs. As part of the safety enhancement of nuclear power plants with VVER type 213 reactors, the leak before break concept has been applied to all NPPs operated in Czech and Slovak Republics. Lessons learned through statistical and mechanistic evaluations are presented.

• OSTI ID: 136776
• Report Number(s): CONF-950740-; ISBN 0-7918-1344-4; TRN: 96:000925
• Resource Relation: Conference: Joint American Society of Mechanical Engineers (ASME)/Japan Society of Mechanical Engineers (JSME) pressure vessels and piping conference, Honolulu, HI (United States), 23-27 Jul 1995; Other Information: PBD: 1995; Related Information: Is Part Of International pressure vessels and piping codes and standards. Volume 1: Current applications; PVP-Volume 313-1; Rao, K.R.; Asada, Yasuhide; Brown, J. [eds.] [and others]; PB: 469 p.
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
WWER-3 REACTOR
REACTOR COOLING SYSTEMS
CZECH REPUBLIC
SLOVAKIA
PIPES
RUPTURES
LEAKS
RELIABILITY
REACTOR SAFETY
NUCLEAR POWER PLANTS
PIPE WHIP
FATIGUE
CRACK PROPAGATION
WATER HAMMER
SEISMIC EFFECTS
SUPPORTS
FRACTURE MECHANICS
STANDARDS
CRACKS