The precise simulation of the reactor core either in steady state or during transients is very important for the safety assessment of nuclear power plants. This requires accurate determination of the parameters that influence the reactor operation. Coupling neutronic and thermal hydraulic schemes are developed to calculate these parameters. In the present paper, a coupling scheme between MCNP6 and ANSYS-FLUENT17.2 codes is proposed to obtain accurate radial and axial temperature distribution and hence pin power distribution for VVER-1000 fuel assembly. The Performance of the developed coupling scheme is investigated in steady state calculations. An iterative process is associated with the exchange of data between codes to meet the convergence criteria. The results obtained demonstrate that the proposed coupling scheme is able to simulate the VVER-1000 fuel assembly accurately. It gives information about thermal and neutronic behavior of the assembly and allows the feedback effects to be accurately modeled. This work is a step forward to establish a consistent methodology to be used in transient calculations.
Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
Research funding: None declared.
Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
ANSYS Inc. (2016). South pointe 2600 ANSYS Drive User’s Guide, 17.2. ANSYS Inc., Canonsburg, PA, USA.Search in Google Scholar
Bahdanovich, R.B., Bogdanova, E.V., Gamtsemlidze, I.D., Nikonov, S.P., and Tikhomirov, G.V. (2017). Test case for VVER-1000 complex modeling using MCU and ATHLET. IOP Conf. Ser. J. Phys. Conf. 781: 012050, https://doi.org/10.1088/1742-6596/781/1/012050.Search in Google Scholar
Bahdanovich, R.B., Bogdanova, E.V., Gamtsemlidze, I.D., Nikonov, S.P., and Tikhomirov, G.V. (2018). VVER-1000 pin cell benchmark for coupled neutronics/thermal-hydraulics calculations: preliminary results. IOP Conf. Ser. J. Phys. Conf. 1133: 012051, https://doi.org/10.1088/1742-6596/781/1/012050.Search in Google Scholar
Brown, F.B. (2006). The makxsf code with Doppler broadening. LA-UR-06–7002. Los Alamos National Laboratory, USA.Search in Google Scholar
Chadwick, M.B., Herman, M., Obložinský, P., Dunn, M.E., Danon, Y., Kahler, A.C., Smith, D.L., Pritychenko, B., Arbanas, G., Arcilla, R., et al.. (2011). ENDF/B-VII.1 nuclear data for science and technology: cross sections, covariance, fission product yields and decay data. Nucl. Data Sheets 112: 2887–2996, https://doi.org/10.1016/j.nds.2011.11.002.Search in Google Scholar
Farkhulina, A.L., Bahdanovich, R.B., and Tikhomirov, G.V. (2018). Development of VVER-1000 pin cell thermal-hydraulic model for MCU/FlowVision coupled calculations. IOP Conf. Ser. J. Phys. Conf. 1133: 012052, https://doi.org/10.1088/1742-6596/1133/1/012052.Search in Google Scholar
Goorley, J.T., James, M.R., Booth, T.E., Brown, F.B., Bull, J.S., Cox, L.J., Durkee, J.W.Jr., Elson, J.S., Fensin, M.L., Forster, R.A.III, et al.. (2013). Initial MCNP6 release overview – MCNP6 version 1.0. Los Alamos National Laboratory Report, LA-UR 13-22934.10.2172/1086758Search in Google Scholar
Gurecky, W.L. (2015). Development of an MCNP6-ANSYS-FLUENT multiphysics coupling capability. Thesis Presented to the Faculty of the Graduate School of the University of Texas at Austin, USA.Search in Google Scholar
Hu, J. and Rizwan-uddin (2008). Coupled neutronics and thermal-hydraulics simulations using MCNP and FLUENT. Trans. Am. Nucl. Soc. 98: 606–608.Search in Google Scholar
Ivanov, A., Sanchez, V., and Imke, U. (2011). Development of a coupling scheme between MCNP5 and SUBCHANFLOW for the pin- and fuel assembly-wise simulation of LWR and innovative reactors. International conference on mathematics and computational methods applied to nuclear science and engineering, Brazil. Rio de Janeiro, RJ.Search in Google Scholar
Królikowski, I.P. and Cetnar, J. (2015). Neutronic and thermal-hydraulic coupling for 3D reactor core modeling combining MCB and FLUENT. NUKLEONIKA 60: 531–536, https://doi.org/10.1515/nuka-2015-0097.Search in Google Scholar
Nikonov, S.P., Pham, P., Romanenko, V.I., Tikhomirov, G.V., and Smirnov, A.D. (2017). Coupled neutronics-thermohydraulic calculation of HPLWR fuel cell using codes MCU/ATHLET. Conference: 27th symposium of AER on VVER reactor physics and reactor safety, Germany, organized by GRS-Germany.Search in Google Scholar
Pelowitz, D.B. (2013). MCNP6 user’s manual version 1.0. Los Alamos National Laboratory Report, LA-CP-13-00634, Rev. 0.Search in Google Scholar
Sanchez, V. and Al-Hamry, A. (2009). Development of a coupling scheme between MCNP and COBRA-TF for the prediction of the pin power of a PWR fuel assembly. American Nuclear Society - ANS; La Grange Park (USA). Interrnational Conference on Advances in Mathematics, Computational Methods, and Reactor Physics; Saratoga Springs, NY, USA.Search in Google Scholar
Tuominen, R. (2015). Coupling SERPENT and open FOAM for neutronics–CFD multi-physics calculations, Thesis submitted for examination for the degree of Master of Science in Technology. Espoo 30.7.2015. AALTO University, Otaniemi, Espoo, Finland.Search in Google Scholar
© 2022 Walter de Gruyter GmbH, Berlin/Boston