Evaluation of steam generator WWER 440 tube integrity criteria
Conference
·
OSTI ID:467909
- 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., IL (United States)
- OSTI ID:
- 467909
- Report Number(s):
- NUREG/CP--0154; ANL--96/14; NEA/CNRA/R--(96)1; CONF-9510423--; ON: TI97004312
- Country of Publication:
- United States
- Language:
- English
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