Published November 1995
| Version v1
Report
Dynamic calculation of the SG 1 feedwater piping within the main feedwater header - penetration segment in the event of an unexpected water hammer
Description
The stress response of the steam generator 1 feedwater piping was calculated for the Dukovany 1 reactor unit. A shock wave arising from the collapse of a steam or air bubble in the main steam header was considered. The mathematical model calculates the eigenfrequencies and resonance states of the piping. Dynamic evaluation showed that the elbow before the hermetic penetration is the most critical point with respect to the piping response to the water hammer. (M.D.). 6 tabs., 4 figs., 8 refs
Availability note (English)
Available from Ustav jaderneho vyzkumu Rez, a.s., 250 68 Rez, Czech Republic.Additional details
Additional titles
- Original title (Czech)
- Dynamicky vypocet potrubi NV do PG1 v useku HNK - pruchodka pri neocekavanem vodnim razu
- Augmented title (English)
- Dukovany 1 reactor
Publishing Information
- Imprint Pagination
- [57 p.].
- Report number
- UJV--10572-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 28059663
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data, Non-conventional Literature
- Descriptors DEI
- DUKOVANY-2 REACTOR; FEEDWATER; MATHEMATICAL MODELS; PIPES; PROBABILISTIC ESTIMATION; SAFETY ANALYSIS; SECONDARY COOLANT CIRCUITS; SHOCK WAVES; STEAM GENERATORS; STRESSES; THEORETICAL DATA
- Descriptors DEC
- BOILERS; COOLING SYSTEMS; DATA; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; INFORMATION; NUMERICAL DATA; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS