Published November 1996
| Version v1
Report
Conclusions from break analyses of the steam and feedwater lines of steam generators 1, 3, and 5 at the Mochovce-1 reactor unit
Description
The starting assumptions, results of calculation and statistical processing of the stress status of the steam generator feedwater piping systems are summarized and the break points are postulated as specified by ANSI 58.2-1980. The results of statistical evaluation of the stress status of the steam line leading from the steam generator encompass normal operation, a seismic event, and an expected steam hammer. The pipe break points were identified. (M.D.)
Availability note (English)
Available from Nuclear Research Institute Rez, 250 68 Rez, Czech RepublicAdditional details
Additional titles
- Original title (Czech)
- Zavery z analyz potrubi pary a napajeci vody PG 1, 3 a 5 EMO, blok 1 na roztrzeni
Publishing Information
- Imprint Pagination
- 30 p.
- Report number
- UJV--10818-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 30020686
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- EARTHQUAKES; MOCHOVCE-1 REACTOR; PIPES; RUPTURES; SAFETY ANALYSIS; SEISMIC EVENTS; STATIC LOADS; STEAM GENERATORS; STRESSES
- Descriptors DEC
- BOILERS; ENRICHED URANIUM REACTORS; FAILURES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SEISMIC EVENTS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- 7 tabs., 7 figs., 28 refs.