Published October 2005
| Version v1
Report
Post-test calculation of primary-to-secondary leak on the PSB-VVER experimental facility. Test 4. Rev. 0
Description
A break on the hot collector of steam generator No. 4 was simulated. PSB/VVER is a 1:300 mockup of the VVER-1000 reactor. The break size was equivalent to 100 mm at a VVER-1000 reactor. The ATHLET MOD2.0 CYCLE B best-estimate computer code was used for the calculations
Availability note (English)
Available (also in the electronic format as a PDF facsimile) from Nuclear Research Institute Rez, 250 68 Rez, Czech Republic; e-mail contact: ret@nri.cz, ric@nri.czAdditional details
Additional titles
- Original title (Czech)
- Post-test vypocet uniku chladiva z primarniho do sekundarniho okruhu u experimentalniho zarizeni PSB-VVER. Test 4. Rev. 0
Publishing Information
- Imprint Pagination
- 66 p.
- Report number
- UJV--12305-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 39011875
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- A CODES; COMPUTER CALCULATIONS; MOCKUP; PIPES; REACTOR ACCIDENT SIMULATION; REACTOR EXPERIMENTAL FACILITIES; RUPTURES; STEAM GENERATORS; WWER TYPE REACTORS
- Descriptors DEC
- BOILERS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FAILURES; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; STRUCTURAL MODELS; THERMAL REACTORS; TUBES; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 6 tabs., 75 figs., 8 refs.