References
- E. Buckingham,"On physically similar systems; illustrations of the use of dimensional equations." Phys. Rev. 4, pp.345-376 (1914). https://doi.org/10.1103/PhysRev.4.345
- F. D'Auria and G. M. Galassi, "Scaling in Nuclear Reactor System Thermal Hydraulics", Nuclear Engineering and Design, 240, pp. 3266-3293 (2010)
- Special Issuedevoted to CSAU, Nuclear Engineering and Design, 119-1, (1990)
- N. Zuber, G. E. Wilson, B. E. Boyack, I. Catton, R. B. Duffey, P. Griffith, K. R. Katsma, G. S. Lellouche, S. Levy, U. S. Rohatgi, W. Wulff, "Evolution of Scale-up Capabilities of Best Estimate Codes", Nuclear Engineering and Design, 119, pp. 97-109 (1990) https://doi.org/10.1016/0029-5493(90)90075-9
- F.D'Auria, G. M. Galassi and L. Moschett "Assessment of scaling criteria adopted in designing nuclear power plants experimental simulators". Nuclear Materials, p.130 (1985)
- M. Ishii, S.T. Revankar, T. Leonardi, A. Dowlati, M.L. Bertodano, I. Babelli, W. Wang, H. Pokharna, V.H. Ransom, R. Viskanta and J.T. Han"The three-level scalingapproach with application to the Purdue University Multi-Dimensional IntegralTest Assembly (PUMA)", Nuclear Engineering and Design 186, pp.177-211 (1989)
- N.Zuber, G.E. Wilson, M. Ishii, W. Wulff, B.E. Boyack, A.E. Dukler, P. Griffith, J.M.Healzer, R.E. Henry, J.R. Lehner, S. Levy, F.J. Moody, M. Pilch, B.R. Sehgal, B.W. Spencer, T.G. Theofanous and J. Valente, "An integrated structure and scaling methodology for severe accident technical issue resolution: development of methodology", Nuclear Engineering and Design 186, pp. 1-21. (1998) https://doi.org/10.1016/S0029-5493(98)00215-5
- N. Zuber, "The effects of complexity, of simplicity and of scaling in thermalhydraulics", Nuclear Engineering and Design, 204, pp. 1-27 (2001). https://doi.org/10.1016/S0029-5493(00)00324-1
- D'Auria, F., Debrecin, N., Galassi, G.M.,. "Outline of the uncertainty methodology based on accuracy extrapolation (UMAE)". Nuclear Technology, 109 (1), pp. 21-38. (1995)
- Special Issue devoted to Scaling, Nuclear Engineering and Design 186, (1998)
- N. Zuber, W.Wulff, U.S. Rohatgi and I. Catton, "Application of fractional scalinganalysis (FSA) to loss of coolant accidents (LOCA) - Part 1: Methodology development" In: Proceedings of the International Top. Meet. On Nuclear Reactor ThermalHydraulics (NURETH-11), Avignon, France (2005)
- W. Wulff, N. Zuber, U.S. Rohatgi, I. Catton, "Application of Fractional ScalingAnalysis (FSA) to Loss of Coolant Accidents (LOCA) - Part 2: System Level Scaling for System Depressurization". Proceedings of the International Top. Meet. On Nuclear Reactor Thermal Hydraulics (NURETH-11), Avignon, France (2005)
- N. Zuber, W.Wulff, U.S. Rohatgi and I. Catton, "Application of fractional scalinganalysis (FSA) to loss of coolant accidents (LOCA),) - Part 3. Componentlevel scaling for peak clad temperature" Proceedings of the International Top. Meet. On Nuclear Reactor Thermal Hydraulics (NURETH-11), Avignon, France (2005)
- A.N. Navahandi, S. Castellana and E.N. Moradkhaniav, "Scaling laws for modeling nuclear reactor systems" Nuclear Science and Engineering, 72 (1982)
- F. D'Auria and P. Vigni, "Proposed set of criteria in designing nuclear power plants experimental simulators" Proceedings of the International Top. Meet. On Nuclear Reactor Thermal Hydraulics (NURETH-3), Newport, USA (1985).
- F.D'Auria, H. Karwat and M. Mazzini,"Planning of counterpart tests in LWR experimental simulators." Proceedings of the ANS National Heat Transfer Conference, Houston, USA.(1988)
- R.C. Borges, F.D'Auria, A.C.M. Alvim, "Independent qualification of the CIAU based on the uncertainty estimate through the simulation of LOBItest BT-02", Kerntechnik 68 (1-2), 7-16.(2003)
- S. Yokobori, H. Nakamura, "Optimized apportion between large-scale nuclear thermal-hydraulic tests and simulation". JAE 27, pp. 461-468 (in Japanese).(2008)
- N.E. Todreas, M.S. Kazimi, "Nuclear Systems". Hemisphere Publishing Corp.(1990)
- L.S. Tong, J.Weisman, J., "Thermal Analysis of Pressurized Water Reactors". ANS La Grange Park, USA (1996).
- H.Ninokata, A. Aritomi, A. (Eds.),. "Sub-channel Analysis in Nuclear Reactors", AESJ,Institute of Applied Energy, ISBN 4-9900222-0-3, pp. 1-301. (1992)
- Y.A. Hassan, H.R. Barsamian, "New-wall modeling for complex flows usingthe large eddy simulation technique in curvilinear coordinates." International Journal of Heat and Mass Transfer 44 (21), pp. 4009-4026. (2001) https://doi.org/10.1016/S0017-9310(01)00047-3
- S. Banerjee, M.G. Ortiz, T.K. Larson, D.L. Reeder, "Scaling in the safety of next generation reactors." Nuclear Engineering and Design vol 186, pp .111-133 (1998) https://doi.org/10.1016/S0029-5493(98)00219-2