Analyses of PACTEL passive safety injection experiments with APROS, CATHARE and RELAP5 codes
Creators
- 1. VTT Energy, Espoo (Finland)
- 2. Lappeenranta University of Technology, Lappeenranta (Finland)
- 3. University of Pisa, Pisa (Italy)
- 4. AEA Technology (United Kingdom)
Description
The European Commission fourth framework programme project 'Assessment of passive safety injection systems of advanced light water reactors' involved experiments on the PACTEL test facility and computer simulations of selected experiments. The experiments focused on the performance of passive safety injection systems (PSIS) of advanced light water reactors (ALWRs) in small break loss-of-coolant accident (SBLOCA) conditions. The PSIS consisted of a core make-up tank (CMT) and two pipelines. A pressure balancing line (PBL) connected the CMT to one cold leg. The injection line (IL) connected it to the downcomer. The project involved 15 experiments in three series. The experiments provided information about condensation and heat transfer processes in the CMT, thermal stratification of water in the CMT, and natural circulation flow through the PSIS lines. The project included validation of three thermal-hydraulic computer codes (APROS, CATHARE and RELAP5). The analyses showed the codes are capable of simulating the overall behaviour of the transients. The codes predicted accurately the core heatup, which occurred when the primary coolant inventory was reduced so much that the core top became free of water. The detailed analyses of the calculation results showed that some models in the codes still need improvements. Especially, further development of models for thermal stratification, condensation and natural circulation flow with small driving forces would be necessary for accurate simulation of the phenomena in the PSIS. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 198
- Journal Issue
- 3
- Journal Page Range
- p. 261-286
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Switzerland
- INIS RN
- 31036091
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- COOLING; DATA PROCESSING; FLUID FLOW; LOSS OF COOLANT; NATURAL CONVECTION; NUCLEAR ENGINEERING; NUCLEAR POWER PLANTS; REACTOR ACCIDENTS; REACTOR SAFETY; TEST FACILITIES; WATER MODERATED REACTORS
- Descriptors DEC
- ACCIDENTS; CONVECTION; ENERGY TRANSFER; ENGINEERING; HEAT TRANSFER; MASS TRANSFER; NUCLEAR FACILITIES; POWER PLANTS; PROCESSING; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL POWER PLANTS
Optional Information
- Notes
- 11 refs.