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Thermal Hydraulic Experiments and Code Validation for LWR SMRs within the European McSAFER Project: Overview of Activities and Current Status
LUT University (LUT) P.O.Box 20, FI-53851 Lappeenranta, Finland, P.O.Box 20.
LUT University (LUT) P.O.Box 20, FI-53851 Lappeenranta, Finland, P.O.Box 20.
LUT University (LUT) P.O.Box 20, FI-53851 Lappeenranta, Finland, P.O.Box 20.
Karlruhe Institute of Technology (KIT) Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany, Hermann-von-Helmholtz-Platz 1.
Vise andre og tillknytning
2023 (engelsk)Inngår i: Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023, American Nuclear Society , 2023, s. 2388-2401Konferansepaper, Publicerat paper (Fagfellevurdert)
Abstract [en]

The EU Horizon 2020 project McSAFER was launched in 2020 to advance the safety research of small modular reactors (SMR) via thermal-hydraulic experiments with related code validation and numerical coupled multi-physics and multi-scale simulations. This paper provides an overview of the thermal-hydraulic experiments and code validation within the project and presents the status of these activities highlighting some of the results already obtained. Experiments are performed at three European laboratories with test facilities dedicated for the investigation of SMR-relevant phenomena. Fundamental heat transfer experiments with boiling up to critical heat flux under forced convection for rod configurations and conditions representative of SMRs are performed with the COSMOS-H facility. Performance of the helical coil steam generator, core cross flow phenomena and the general behavior of an SMR operating with natural circulation are investigated with the MOTEL facility. Heat transfer phenomena are investigated in conditions relevant for SMRs also in forced to natural circulation transients with the HWAT facility. Selected thermal hydraulic system, subchannel and computational fluid dynamics (CFD) codes are validated with the experimental data.

sted, utgiver, år, opplag, sider
American Nuclear Society , 2023. s. 2388-2401
Emneord [en]
code validation, experiments, light water reactors, small modular reactors
HSV kategori
Identifikatorer
URN: urn:nbn:se:kth:diva-353505DOI: 10.13182/NURETH20-40209Scopus ID: 2-s2.0-85202954309OAI: oai:DiVA.org:kth-353505DiVA, id: diva2:1899180
Konferanse
20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023, Washington, United States of America, Aug 20 2023 - Aug 25 2023
Merknad

 Part of ISBN 9780894487934

QC 20240924

Tilgjengelig fra: 2024-09-19 Laget: 2024-09-19 Sist oppdatert: 2024-09-24bibliografisk kontrollert

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Li, HaipengGrishchenko, Dmitry

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