Analyses of PACTEL passive safety injection experiments with APROS, CATHARE and RELAP5 codes

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...

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Bibliographic Details
Published in:Nuclear engineering and design 2000-06, Vol.198 (3), p.261-286
Main Authors: Tuunanen, Jari, Vihavainen, Juhani, D'Auria, Francesco, Frogheri, Monica, Galassi, G.M, Kimber, George, Lillington, John, Alien, Elizabeth, Williams, T.G
Format: Article
Language:English
Subjects:
Applied sciences
Computer simulation
Computer software
Condensation
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fission nuclear power plants
Heat transfer
Installations for energy generation and conversion: thermal and electrical energy
Nuclear reactor accidents
Pipelines
Reactor cores
Risk assessment
Thermal stratification
Transients
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Summary: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.
ISSN:0029-5493
1872-759X
DOI:10.1016/S0029-5493(99)00312-X