Evaluation of steam generator WWER 440 tube integrity criteria

Conference · Sat Feb 01 00:00:00 EST 1997

OSTI ID:467909

Splichal, K; Otruba, J; Burda, J ^[1]

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1. Nuclear Research Institute Rez plc. (Czechoslovakia)

The main corrosion damage in WWER steam generators under operating conditions has been observed on the outer surface of these tubes. An essential operational requirement is to assure a low probability of radioactive primary water leakage, unstable defect development and rupture of tubes. In the case of WWER 440 steam generators the above requirements led to the development of permissible limits for data evaluation of the primary-to-secondary leak measurements and determination of acceptable values for plugging of heat exchange tubes based on eddy current test (ECT) inspections.

• Research Organization: CH2M Hill, Gainesville, FL (United States); Argonne National Lab. (ANL), Argonne, IL (United States)
• OSTI ID: 467909
• Report Number(s): NUREG/CP-0154; ANL-96/14; NEA/CNRA/R-(96)1; CONF-9510423-; ON: TI97004312; TRN: 97:008375
• Resource Relation: Conference: CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants, Oak Brook, IL (United States), 30 Oct - 2 Nov 1995; Other Information: PBD: Feb 1997; Related Information: Is Part Of Proceedings of the CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants; Diercks, D.R. [Argonne National Lab., IL (United States)]; PB: 621 p.
• Country of Publication: United States
• Language: English

Related Subjects

21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
TUBES
DEFECTS
EVALUATION
NONDESTRUCTIVE TESTING
WWER-3 REACTOR
STEAM GENERATORS
CORROSION
PLUGGING