The primary circuit materials properties results analysis performed on archive material used in NPP V-1 and Kola NPP Units 1 and 2

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

OSTI ID:489309

Kupca, L; Beno, P ^[1]

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1. Nuclear Power Plants Research Institute Inc., Trnava (Slovakia)

A very brief summary is provided of a primary circuit piping material properties analysis. The analysis was performed for the Bohunice V-1 reactor and the Kola-1 and -2 reactors. Assessment was performed on Bohunice V-1 archive materials and primary piping material cut from the Kola units after 100,000 hours of operation. Main research program tasks included analysis of mechanical properties, corrosion stability, and microstructural properties. Analysis results are not provided.

• 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: 489309
• Report Number(s): NUREG/CP-0155; CONF-9510432-; ON: TI97004806; TRN: 97:011449
• 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

21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
PIPES
MATERIALS TESTING
BOHUNICE V-1 REACTOR
KOLA-1 REACTOR
KOLA-2 REACTOR
PRIMARY COOLANT CIRCUITS