Global reference list
This page gathers all the sources cited throughout the OpenSTREAM documentation in one convenient place. Whether you’re tracing a model back to its theoretical roots or looking for further reading, this is your go-to resource for exploring the academic and technical foundations behind the code.
C. Adamsson and J.M. Le Corre. Transient dryout prediction using a computationally efficient method for sub-channel film-flow analysis. Nuclear Engineering and Design, 280:316–325, 2014. URL: https://www.sciencedirect.com/science/article/pii/S0029549314005081, doi:https://doi.org/10.1016/j.nucengdes.2014.09.012.
Carl Adamsson and Jean-Marie Le Corre. Modeling and validation of a mechanistic tool (mefisto) for the prediction of critical power in bwr fuel assemblies. Nuclear Engineering and Design, 241(8):2843–2858, 2011. URL: https://www.sciencedirect.com/science/article/pii/S0029549311000847, doi:https://doi.org/10.1016/j.nucengdes.2011.01.033.
D. Bestion. The physical closure laws in the cathare code. Nuclear Engineering and Design, 124(3):229–245, 1990. URL: https://www.sciencedirect.com/science/article/pii/0029549390902948, doi:https://doi.org/10.1016/0029-5493(90)90294-8.
Yu. A. Bezrukov, V. I. Astakhov, and V. G. Brantov. Experimental investigation and statistical analysis of data on burnout in rod bundles for water-moderated water-cooled reactors. Teploenergetika, 23:67–70, 1976. English translation available in Thermal Engineering.
L. Biasi, G. C. Clerici, S. Garribba, R. Sala, and A. Tozzi. Studies on burnout. part 3: a new correlation for round ducts and uniform heating and its comparison with world data. Energ. Nucleare (Milan), 14(9):530–536, September 1966.
F.W Dittus and L.M.K Boelter. Heat transfer in automobile radiators of the tubular type. Publications in Engineering, 2:443–461, 930.
G. F. Hewitt and A. H. Govan. Phenomenological modelling of non‑equilibrium flows with phase change. International Journal of Heat and Mass Transfer, 33(2):229–242, February 1990. URL: https://doi.org/10.1016/0017-9310(90)90094-B, doi:10.1016/0017-9310(90)90094-B.
G. S. Lellouche and B. A. Zolotar. A mechanistic model for predicting two-phase void fraction for water in vertical tubes, channels and rod bundles. Technical Report EPRI NP-2246-SR, Electric Power Research Institute, Palo Alto, California, February 1982. URL: https://www.nrc.gov/docs/ML2001/ML20010E663.pdf.
William H. McAdams. Heat Transmission. McGraw-Hill, New York, NY, 1942. Includes correlation for turbulent single-phase convection.
Tomio Okawa, Akio Kotani, Isao Kataoka, and Masanori Naito. Prediction of critical heat flux in annular flow using a film flow model. Journal of Nuclear Science and Technology, 40(6):388–396, June 2003. URL: https://doi.org/10.1080/18811248.2003.9715370, doi:10.1080/18811248.2003.9715370.
Tomio Okawa, Akio Kotani, Isao Kataoka, and Masanori Naitoh. Prediction of the critical heat flux in annular regime in various vertical channels. Nuclear Engineering and Design, 229(2):223–236, 2004. URL: https://www.sciencedirect.com/science/article/pii/S0029549304000512, doi:https://doi.org/10.1016/j.nucengdes.2004.01.005.
W. E. Ranz and W. R. Marshall. Evaporation from drops. part i. Chemical Engineering Progress, 48(3):141–146, March 1952.
D. G. Reddy and others. Two-phase friction multiplier for high pressure steam-water flow. Technical Report EPRI-NP-2522, Electric Power Research Institute, Palo Alto, California, July 1982.
Warren M. Rohsenow, James P. Hartnett, and Young I. Cho, editors. Handbook of Heat Transfer. McGraw-Hill, New York, 3 edition, 1998. ISBN 0-07-0535558. A comprehensive handbook edited by Rohsenow, Hartnett, and Cho.
P. Saha and N. Zuber. Point of net vapor generation and vapor void fraction in subcooled boiling. In Proceedings of the International Heat Transfer Conference (IHTC-5). Tokyo, Japan, December 1973. Georgia Institute of Technology, Atlanta, Scripta Book Co. Conference paper; OSTI ID 4195144. URL: https://www.osti.gov/biblio/4195144.
L. Sanmiguel Gimeno, S. P. Walker, G. F. Hewitt, J.-M. Le Corre, A. Dasgupta, and M. Ahmad. Validation and cross‑verification of three mechanistic codes for annular two‑phase flow simulation and dryout prediction. In Proceedings of NURETH‑16 (16th International Topical Meeting on Nuclear Reactor Thermalhydraulics). Chicago, IL, USA, 2015.
G. B. Wallis. One-Dimensional Two-Phase Flow. McGraw-Hill, New York, 1st edition, 1969. ISBN 9780070679429.
Elisabeth K. Walter. Derivation and open source implementation of a simplified one-dimensional two-fluid model. Master's thesis, KTH Royal Institute of Technology, Stockholm, Sweden, 2024. URL: https://www.diva-portal.org/smash/record.jsf?pid=diva2:1888131.
U. Windecker. Spacer model for prediction of axial dryout locations in annular flow. Technical Report SECRC/B/TR-99/047E, ABB (ASEA Brown Boveri), Sweden, 1999.
J.-M. Le Corre. Non-equilibrium modeling of disturbance waves with phase change in fuel bundle. In Proceedings of the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19). Brussels, Belgium, March 6–11 2022.
Jean-Marie Le Corre. Phenomenological model of disturbance waves in annular two-phase flow. International Journal of Multiphase Flow, 151:104057, 2022. URL: https://www.sciencedirect.com/science/article/pii/S0301932222000696, doi:https://doi.org/10.1016/j.ijmultiphaseflow.2022.104057.
Jean-Marie Le Corre. Mechanistic prediction of westinghouse triton11® bwr fuel critical power with mefisto-t subchannel analysis code. Nuclear Engineering and Design, 429:113613, 2024. URL: https://www.sciencedirect.com/science/article/pii/S0029549324007131, doi:https://doi.org/10.1016/j.nucengdes.2024.113613.
Jean-Marie Le Corre, Jason Chan, Elisabeth Walter, Evan T. Hurlburt, and Roman W. Morse. Openstream: a new open-source platform for two-phase flow model development. In Proceedings of the 12th International Conference on Multiphase Flow (ICMF 2025). Toulouse, France, May 12–16 2025. URL: https://openstream-solvers.github.io/openstream/_static/publications/LeCorre2025ICMF.pdf.
Jean-Marie Le Corre, Jason Chan, Elisabeth Walter, Evan T. Hurlburt, and Roman W. Morse. Openstream: an open-source platform for two-phase flow modeling and simulation. In Proceedings of the 21st International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-21). Busan, Korea, August 31–September 5 2025. URL: https://openstream-solvers.github.io/openstream/_static/publications/LeCorre2025OpenSTREAM.pdf.