Published October 2002
| Version v1
Report
Thermal hydraulic analysis of the formation of 'cold plumes' during a primary-to-secondary leak in the event of rupture of 3 steam generator tubes with operator intervention (SGTR1, SGTR2, SGTR3 and SGTR4 processes)
Description
Chapter 2 describes the codes used, i.e. REMIX and NEWMIX. Chapters 3-6 are devoted to the accidents analyzed. Each chapter describes the development of the accident as calculated by RELAP5 together with the boundary and initial conditions and results of the calculation. Chapter 7 contains concluding remarks. The analyses provide input data (coolant temperature at the internal wall of the reactor vessel, viz. both on the cold plume axis and beyond the cold plume) for subsequent mechanical analysis, enabling us to assess the effect of the accident on a potential initiation of a sudden break from cracks that might be present in the reactor pressure vessel wall. (P.A.)
Availability note (English)
Available from Nuclear Research Institute Rez, 250 68 Rez, Czech Republic; e-mail contact: ret@nri.czAdditional details
Additional titles
- Original title (Czech)
- Termohydraulicka analyza tvorby 'studenych jazyku' behem uniku z primarniho do sekundarniho okruhu pri prasknuti 3 trubek PG se zasahy operatora (procesy SGTR1, SGTR2, SGTR3 and SGTR4)
Publishing Information
- Imprint Pagination
- 33 p.
- Report number
- UJV--11805-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 37058256
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; COOLANTS; MATHEMATICAL MODELS; N CODES; PRESSURE VESSELS; R CODES; REACTOR SAFETY; SAFETY ANALYSIS; STEAM GENERATORS; TEMPERATURE DISTRIBUTION; THERMAL HYDRAULICS; WWER TYPE REACTORS
- Descriptors DEC
- BOILERS; COMPUTER CODES; CONTAINERS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 18 figs., 9 refs.