Published December 2005
| Version v1
Report
Validation of RELAP5-3D computer code on the MSLB problem within the 6th dynamic AER benchmark. Rev. 0
Description
The benchmark was concerned with a two-side break of a main steam line at a NPP with VVER 440/213 reactor units. RELAP5-3D was tested on an input deck for the Dukovany NPP. The input model is a detailed 6-loop model, modified based on specifications of the 6th dynamic AER benchmark. The input deck stems from the 'international' three-loop input deck for the Jaslovske Bohunice NPP, prepared within the IAEA regional programme 'Safety Assessment of VVER-440/213'. Furthermore the model was extended and modified with respect to Dukovany specifications and needs for more detailed analyses. (P.A.)
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)
- Validace vypocetniho programu RELAP5-3D na uloze MSLB v ramci dynamickeho benchmarku 6th AER. Revize 0
Publishing Information
- Imprint Pagination
- [52 p.]
- Report number
- UJV--12344-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 39110851
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- DATA BASE MANAGEMENT; DATA COMPILATION; FIRE FIGHTING; FIRES; NUCLEAR POWER PLANTS; OECD; POWER REACTORS; R CODES; REPORTING REQUIREMENTS; WWER TYPE REACTORS
- Descriptors DEC
- COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; INFORMATION; INTERNATIONAL ORGANIZATIONS; MANAGEMENT; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 8 tabs., 56 figs., 12 refs.