System thermal-hydraulic modelling of the phénix dissymmetric test benchmark
| Autor: | Adam Kraus, A. Del Nevo, J. W. Thomas, Acacia J. Brunett, N. Girault, Gianfranco Caruso, Xiaoye Wang, Fabio Giannetti, F. Alcaro, B. Grosjean, Vincenzo Narcisi, A. Gerschenfeld |
|---|---|
| Přispěvatelé: | Department of Informatics and System Sciences (Sapienza University of Rome), Università degli Studi di Roma 'La Sapienza' = Sapienza University [Rome], Italian National agency for new technologies, Energy and sustainable economic development [Frascati] (ENEA), Nuclear Research and Consultancy Group, Karlsruhe Institute of Technology (KIT), Argonne National Laboratory [Lemont] (ANL), Institut de Radioprotection et de Sûreté Nucléaire (IRSN), Université Paris-Saclay, Narcisi, V., Giannetti, F., Del Nevo, A., Alcaro, F., Wang, X., Kraus, A., Brunett, A., Thomas, J., Girault, N., Grosjean, B., Caruso, G., Gerschenfeld, A. |
| Jazyk: | angličtina |
| Rok vydání: | 2019 |
| Předmět: |
Nuclear and High Energy Physics
Liquid metal Source code Computer science 020209 energy media_common.quotation_subject Nuclear engineering Shutdown 02 engineering and technology 01 natural sciences 7. Clean energy Phénix system thermal-hydraulics sodium cooled reactors SESAME dissymmetric test 010305 fluids & plasmas Set (abstract data type) Thermal hydraulics 0103 physical sciences 0202 electrical engineering electronic engineering information engineering General Materials Science Safety Risk Reliability and Quality Waste Management and Disposal media_common [PHYS]Physics [physics] Mechanical Engineering Frame (networking) Experimental data Nuclear Energy and Engineering Benchmark (computing) |
| Zdroj: | Nuclear Engineering and Design Nuclear Engineering and Design, Elsevier, 2019, 353, pp.110272. ⟨10.1016/j.nucengdes.2019.110272⟩ |
| ISSN: | 0029-5493 |
| DOI: | 10.1016/j.nucengdes.2019.110272⟩ |
| Popis: | International audience; Phénix is a French pool-type sodium-cooled prototype reactor; before the definitive shutdown, occurred in 2009, a final set of experimental tests are carried out in order to increase the knowledge on the operation and the safety aspect of the pool-type liquid metal-cooled reactors. One of the experiments was the Dissymmetric End-of-Life Test which was selected for the validation benchmark activity in the frame of SESAME project. The computer code validation plays a key role in the safety assessment of the innovative nuclear reactors and the Phénix dissymmetric test provides useful experimental data to verify the computer codes capability in the asymmetric thermal-hydraulic behaviour into a pool-type liquid metal-cooled reactor. This paper shows the comparison of the outcomes obtained with six different System Thermal-Hydraulic (STH) codes RELAP5-3D©, SPECTRA, ATHLET, SAS4A/SASSYS-1, ASTEC-Na and CATHARE. The nodalization scheme of the reactor was individually achieved by the participants; during the development of the thermal-hydraulic model, the pool nodalization methodology had a special attention in order to investigate the capability of the STH codes to reproduce the dissymmetric effects which occur in each loop and into pools, caused by the azimuthal asymmetry of the boundary conditions. The modelling methodology of the participants is discussed and the main results are compared in this paper to obtain useful guide lines for the future modelling of innovative liquid metal pool-type reactors. © 2019 Elsevier B.V. |
| Databáze: | OpenAIRE |
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