Published June 1995
| Version v1
Report
Input model of the Temelin NPP for RELAP5/MOD3.1. Steady state and test calculation
Description
The input model used previously for the RELAP5/MOD3 code was adapted to the new version MOD 3.1. Based on the data of the new fuel, the reactor kinetics was modified and new variants of the model for the fuel cycle beginning and end were set up. The steam generator feedwater piping was fully modelled on the secondary circuit, which allows accidents associated with feedwater piping rupture to be analyzed. The steady state of the system for a 100% power was refined for the new model, the input model was tested, and dynamic calculations were performed. (author). 2 tabs., 58 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)
- Vstupni model JE Temelin pro RELAP5/MOD3.1. Stacionarni stav a overovaci vypocet
Publishing Information
- Imprint Pagination
- [45 p.].
- Report number
- UJV--10477-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 28021815
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Numerical Data, Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; DESIGN BASIS ACCIDENTS; R CODES; TEMELIN-1 REACTOR; THEORETICAL DATA
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS