Simulation of long-term cooling in the VVER-640 power plant after a large break LOKA on the PACTEL facility
Creators
- 1. Lappeenranta Univ. of Technology (Finland). Dept. of Energy Technology
- 2. Obninsk Institute of Nuclear Power Engineering, Oblinsk (Russian Federation)
Description
The present report gives a short introduction to the safety features of the new Russian VVER-640 reactor design. In order to analyze the complex thermal hydraulic phenomena during long-term cooling after a large-break LOCA, experiments will be carried out in the PACTEL facility. For preparation, pre-test calculations were performed using the RELAPS/MOD3.2 computer code. The main part of the report discusses the results obtained by the program. The structure and options used in the input deck, as well as the efforts of code application to the simulation of proposed experiments are reviewed. A short sensitivity study is provided on the calculated results. Finally, conclusions are drawn for the code capabilities to represent the expectable trends in the upcoming tests. (orig.)
Availability note (English)
Available from INIS in electronic form; Also available from Lappeenranta Univ. of Technology, Dept. of Energy Technology, P.O.Box 20, FIN-53851 Lappeenranta, Finland
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- ISBN
- 951-764-410-8
- Imprint Pagination
- 43 p.
- Report number
- LTKK-EN-A--43
INIS
- Country of Publication
- Finland
- Country of Input or Organization
- Finland
- INIS RN
- 32034169
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- HYDRAULICS; LOSS OF COOLANT; REACTOR COOLING SYSTEMS; REACTOR SAFETY EXPERIMENTS; SAFETY ENGINEERING; SCALE MODELS; TEST FACILITIES; THERMAL ANALYSIS; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENERGY SYSTEMS; ENGINEERING; ENRICHED URANIUM REACTORS; FLUID MECHANICS; MECHANICS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; STRUCTURAL MODELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs.