Neutronic and thermal-hydraulic coupling for 3D reactor core modeling combining MCB and fluent

• Authors: Igor P. Królikowski , Jerzy Cetnar
• Languages of publication: EN

Abstracts

EN

Three-dimensional simulations of neutronics and thermal hydraulics of nuclear reactors are a tool used to design nuclear reactors. The coupling of MCB and FLUENT is presented, MCB allows to simulate neutronics, whereas FLUENT is computational fluid dynamics (CFD) code. The main purpose of the coupling is to exchange data such as temperature and power profile between both codes. Temperature required as an input parameter for neutronics is significant since cross sections of nuclear reactions depend on temperature. Temperature may be calculated in thermal hydraulics, but this analysis needs as an input the power profile, which is a result from neutronic simulations. Exchange of data between both analyses is required to solve this problem. The coupling is a better solution compared to the assumption of estimated values of the temperatures or the power profiles; therefore the coupled analysis was created. This analysis includes single transient neutronic simulation and several steady-state thermal simulations. The power profile is generated in defined points in time during the neutronic simulation for the thermal analysis to calculate temperature. The coupled simulation gives information about thermal behavior of the reactor, nuclear reactions in the core, and the fuel evolution in time. Results show that there is strong influence of neutronics on thermal hydraulics. This impact is stronger than the impact of thermal hydraulics on neutronics. Influence of the coupling on temperature and neutron multiplication factor is presented. The analysis has been performed for the ELECTRA reactor, which is lead-cooled fast reactor concept, where the coolant fl ow is generated only by natural convection

Keywords

EN

code coupling · modeling · Monte Carlo · neutronics · nuclear reactor · thermal hydraulics

• Publisher: De Gruyter Open
• Journal: Nukleonika
• Year: 2015
• Volume: 60
• Issue: 3
• Pages: 531-536

Dates

published

1 - 9 - 2015

accepted

20 - 5 - 2015

online

25 - 9 - 2015

received

29 - 9 - 2014

Contributors

author

Igor P. Królikowski

• Faculty of Energy and Fuels, AGH University of Science and Technology, 30 Mickiewicza Ave., 30-059 Krakow, Poland

author

Jerzy Cetnar

• Faculty of Energy and Fuels, AGH University of Science and Technology, 30 Mickiewicza Ave., 30-059 Krakow, Poland,

References

• 1. Yan, Y., Rizwan-uddin, & Kim, K. (2008). A coupled CFD-system code development and application. PHYSOR, Interlaken, Switzerland.
• 2. Reiss, T., Fehér, S., & Czifrus, S. (2008). Coupled neutronics and thermo hydraulics calculations with burn-up for HPLWRs. Progr. Nucl. Energy, 50, 52-61.[WoS]
• 3. Seker, V., Thomas, J. W., & Downar, T. J. (2007). Reactor physics simulations with coupled Monte Carlo calculations and computational fl uid dynamics. In Proceedings of International Conference on Emerging Nuclear Energy Systems (ICENES 2007).
• 4. Breitkreutz, H., Rohrmoser, A., & Petry, W. (2010). 3-Dimensional coupled neutronic and thermalhydraulic calculations for a compact core combining MCNPX and CFX. IEEE Trans. Nucl. Sci., 57(6), 3667-3671.[WoS]
• 5. Jianwei, Hu, & Rizwan-uddin. (2008). Coupled neutronics and thermal-hydraulics simulations using MCNP and FLUENT. Advancements in multi- -physics reactor simulation. USA.
• 6. Fluent Inc. (2006). FLUENT 6.3 User’s Guide. Fluent Inc.
• 7. Cetnar, J. (2006). User Manual for MCB 5. Kraków: AGH WFiIS.
• 8. MCNP - A general Monte Carlo code n-particle transport code, Version 5. (2008). X-5 Monte Carlo Team.
• 9. Wallenius, J. (2010). Lead cooled fast reactors. In Proceedings of LEADER Workshop on KTH Stockholm, Department of Reactor Physics.
• 10. Wallenius, J., Suvdantsetseg, E., & Fokau, A. (2011). ELECTRA: European Lead cooled Training Reactor. Stockholm: Reactor Physics, KTH.
• 11. Wallenius, J. (2010). Physical properties of lead. In Proceedings of LEADER Workshop on KTH Stockholm, Department of Reactor Physics.

Identifiers

DOI

10.1515/nuka-2015-0097