Numerical simulation methods of fires in nuclear power plants
Creators
- 1. Technical Research Centre of Finland, Espoo (Finland). Fire Technology Lab.
Description
Fire is a significant hazard to the safety of nuclear power plants (NPP). Fire may be serious accident as such, but even small fire at a critical point in a NPP may cause an accident much more serious than fire itself. According to risk assessments a fire may be an initial cause or a contributing factor in a large part of reactor accidents. At the Fire Technology and the the Nuclear Engineering Laboratory of the Technical Research Centre of Finland (VTT) fire safety research for NPPs has been carried out in a large extent since 1985. During years 1988-92 a project Advanced Numerical Modelling in Nuclear Power Plants (PALOME) was carried out. In the project the level of numerical modelling for fire research in Finland was improved by acquiring, preparing for use and developing numerical fire simulation programs. Large scale test data of the German experimental program (PHDR Sicherheitsprogramm in Kernforschungscentral Karlsruhe) has been as reference. The large scale tests were simulated by numerical codes and results were compared to calculations carried out by others. Scientific interaction with outstanding foreign laboratories and scientists has been an important part of the project. This report describes the work of PALOME-project carried out at the Fire Technology Laboratory only. A report on the work at the Nuclear Engineering Laboratory will be published separatively. (au)
Availability note (English)
MF available from INIS under the Report Number.
Files
Additional details
Additional titles
- Original title (Finnish)
- Ydinvoimalaitosten tulipalojen laskentamenetelmaet
Publishing Information
- ISBN
- 951-38-4210-X
- Imprint Pagination
- 79 p.
- Report number
- VTT-TIED--1396
INIS
- Country of Publication
- Finland
- Country of Input or Organization
- Finland
- INIS RN
- 24075220
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- B CODES; COMPUTERIZED SIMULATION; F CODES; FIRES; H CODES; HDR REACTOR; REACTOR ACCIDENTS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; TESTING
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; COMPUTER CODES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS