Published December 2000
| Version v1
Report
Calculations of the Temelin containment by the RALOC code. Rev. 0
Description
Analyzing a maximum design basis accident, the calculations were performed within the testing of a newly developed model of the Temelin containment for RALOC MOD 4.0AG. Three calculations were carried out, one basic and two complementary. The calculations indicated a considerable effect of the thermal structures on the resultant parameters and ineffectiveness of the chosen method of spray system modelling during the accident types treated. (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)
- Vypocty ochranne obalky JE Temelin programem RALOC. Revize 0
Publishing Information
- Imprint Pagination
- 34 p.
- Report number
- UJV--11559-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 37002776
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; CONTAINMENT; DESIGN BASIS ACCIDENTS; ECCS; R CODES; TEMELIN-1 REACTOR
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- Developed within the Czech Ministry of Industry and Trade project 'Increasing the efficiency and safety of operation of nuclear power plants'. 5 tabs., 22 figs., 8 refs.