Published March 1997
| Version v1
Report
Assessment of the probability of WWER 440 heat transfer tube break
Description
An overview is presented of the state of the art in the steam generator tube integrity assessment. Damage of the tubes is evaluated in terms of the nature of the defects and their occurrence in the operating conditions. The resistance of the tube against break was measured by the burst test method, the thinning of the WWER steam generator tubes was determined by the eddy current method. This parameters was used in correlation with the observed critical pressure to tube break in order to derive the limits for blinding. The probability of WWER steam generator tube break corresponding to the limits for blinding was determined for the Mochovce NPP for the 3-year and 4-year periods of in-service inspections. (author)
Availability note (English)
Available from Nuclear Research Institute Rez, 250 68 Rez, Czech RepublicAdditional details
Additional titles
- Original title (Czech)
- Hodnoceni pravdepodobnosti roztrzeni teplosmennych trubek VVER 440
Publishing Information
- Imprint Pagination
- [15 p.]
- Report number
- UJV--10901-M
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 30030714
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- CRITICAL PRESSURE; DEFECTS; EDDY CURRENT TESTING; HEAT TRANSFER; IN-SERVICE INSPECTION; MOCHOVCE-1 REACTOR; PIPES; PROBABILISTIC ESTIMATION; RUPTURES; STEAM GENERATORS; TUBES
- Descriptors DEC
- BOILERS; ELECTROMAGNETIC TESTING; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FAILURES; INSPECTION; MATERIALS TESTING; NONDESTRUCTIVE TESTING; PHYSICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; TESTING; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- 1 tabs., 7 figs., 8 refs.