Passive heat transfer in small and modular reactors
SPLETNA STRAN V DELU !!!!
Oznaka in naziv projekta
L7-70126
Passive heat transfer in small and modular reactors
- Ivo Kljenak (R4)
Logotipi ARIS in drugih sofinancerjev
Projektna skupina
- Vodja projekta: Ivo Kljenak
Sodelujoče raziskovalne organizacije:
Sestava projektne skupine:
Ivo Kljenak, Iztok Tiselj, Andrej Prošek, Janez Kokalj, Zoran Petrič, Matej Tekavčič, Leon Cizelj, Aljoša Gajšek
Project description
Small Modular Reactors (SMRs) offer a promising option for expanding the usability, versatility, reliability and safety of nuclear power in the future. Many proposed SMR designs incorporate passive safety systems that can provide important safety functions, including heat removal during accident conditions. By requiring limited external power, system support and operator actions, these systems have the potential to provide a high level of reactor safety and reliability. However, the thermal-hydraulic phenomena governing their performance are often driven by relatively small forces, making them difficult to model accurately and creating uncertainties in safety analyses.
Therefore, the project aims to improve the understanding and modelling of passive heat transfer phenomena in light-water SMRs. Using Computational Fluid Dynamics (CFD) and thermal-hydraulic system codes, the project will simulate experiments representing key passive safety systems on both the local and system scale, assess the capability of current modelling approaches and identify critical gaps in existing models. Particular attention will be devoted to steam condensation in safety condenser tubes, external cooling of the reactor pressure vessel and gravity-driven safety injection from accumulators.
Simulation results will be validated against experimental data generated within the European EASI-SMR project. The research will support the refinement of existing heat transfer models and enhance the reliability of simulation tools used for SMR safety analyses. The developed and validated models will serve as building blocks for future digital twins, supporting the design, assessment and safe operation of small modular reactors.
Work programme
The work programme is divided into three parts, each focusing on a key phenomenon relevant to passive safety systems of small modular reactors (SMRs). The work combines CFD simulations using OpenFoam, system-level thermal-hydraulic simulations using RELAP5 and experimental data available through the European EASI-SMR project.
1. Steam condensation in a classical safety condenser tube
Goal: To characterize and model steam condensation and heat transfer in safety condenser tubes under conditions relevant to SMR passive safety systems.
Two sets of experiments in the SACO facility will be simulated. The first, performed in the COSAC condensation tube, covers a broad range of steam pressures and temperatures and will be used to compare experimental heat-transfer data with system-code predictions. The second, performed in the PRECISE condensation tube, provides high-resolution data for validation of system and CFD models of film condensation, including conditions with and without non-condensable gases. The analyses will help to distinguish uncertainties related to condensation and cooling from those associated with boiling in the surrounding pool.
2. Reactor pressure vessel external cooling
Goal: To analyse external cooling of the reactor pressure vessel (RPV) under in-vessel retention (IVR) conditions and assess the capability of computational models to reproduce experimental results.
The experiments investigate external cooling of the RPV under pool boiling and thermosiphon conditions. CFD simulations will focus on the influence of heat-flux distribution, cooling-system geometry, coolant conditions and water level on the cooling rate of the vessel wall. A system-code model will additionally assess the applicability of the approach to accident simulations of an entire SMR.
3. Gravity-driven injection from accumulators
Goal: To assess the capability of system and CFD codes to model gravity-driven emergency injection during a loss-of-coolant accident.
System-code simulations will investigate the GRADAC experiment and assess the applicability of gravity-driven injection modelling to entire SMR systems over longer time periods. CFD simulations will focus on local phenomena, including liquid-surface disturbances caused by steam injection, the effect of different sparger configurations, mixing of the warmer upper liquid layer, steam condensation and heat absorption by the surrounding walls.
Časovnica
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Dokumenti projekta
Izbrane reference
[1] S. Manojlović, B. Krajnc, A. J. Billington, “Overview of the Root cause analysis of the Krško SI-53 piping leakage”, Proc. Int. Conf. Nuclear Energy for New Europe (NENE 2025), Bled, Slovenia, September 8-11, Nuclear Society of Slovenia, 2025.
[2] B. Žužek, B. Šetina Batič, J. Burja, S. Manojlović, A. Parsi, C. Cmar, “Failure Analysis of SI-53 Line Crack in NEK Reactor Cooling System”, Proc. Int. Conf. Nuclear Energy for New Europe (NENE 2025), Bled, Slovenia, September 8-11, Nuclear Society of Slovenia, 2025.
[3] I. Tiselj, M. Draksler, B. Mikuž, L. Cizelj, M. Halilović, S. Manojlović, B. Krajnc, “Analysis of Temperature and Displacement Measurements on Reactor Vessel Safety Injection Lines in NPP Krško”, Proc. Int. Conf. Nuclear Energy for New Europe (NENE 2025), Bled, Slovenia, September 8-11, Nuclear Society of Slovenia, 2025.
[4] M. Draksler, I. Tiselj, B. Mikuž, J. Kren, L. Cizelj, D. Grgić, S. Šadek, P. Družijanić, “Supporting CFD thermal cycling and thermal stratification analyses in SI-53 line”, Proc. Int. Conf. Nuclear Energy for New Europe (NENE 2025), Bled, Slovenia, September 8- 11, Nuclear Society of Slovenia, 2025.
[5] M. Halilovič, A. Maček, B. Starman, S. El Shawish, O. Costa, L. Cizelj, “Krško SI-53 Piping Leakage: Supporting Mechanical Analyses in SI-53 Line”, Proc. Int. Conf. Nuclear Energy for New Europe (NENE 2025), Bled, Slovenia, September 8-11, Nuclear Society of Slovenia, 2025.