Published December 1993
| Version v1
Report
Calculation of transients for nuclear power plants with WWER-1000 type reactors
Description
Calculations of accidents associated with failure of the main circulation pumps were performed within the development and testing of thermohydraulic codes and a thermohydraulic analysis of the Temelin NPP. Codes CATHARE, MOST and RELAP were employed. The input model of a WWER-1000 type nuclear power plant is described. The results of the analysis are tentative only because of lack of input data. Despite the differences in the models and input data sources, for the secondary part in particular, a certain agreement is found between the results obtained with the CATHARE code and the RELAP code. (J.B.). 1 tab., 34 figs., 3 refs
Availability note (English)
Available from Ustav jaderneho vyzkumu Rez a.s., 250 68 Rez, Czech Republic.Additional details
Additional titles
- Original title (Czech)
- Vypocty prechodovych procesu v JE s VVER-1000
Publishing Information
- Imprint Pagination
- 85 p.
- Report number
- UJV--10114-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 27041731
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; LOSS OF FLOW; MATHEMATICAL MODELS; PRIMARY COOLANT CIRCUITS; SECONDARY COOLANT CIRCUITS; TRANSIENTS; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS