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http://dx.doi.org/10.5516/NET.02.2012.711

SCALING ANALYSIS IN BEPU LICENSING OF LWR  

D'auria, Francesco (University of Pisa)
Lanfredini, Marco (University of Pisa)
Muellner, Nikolaus (University of Pisa)
Publication Information
Nuclear Engineering and Technology / v.44, no.6, 2012 , pp. 611-622 More about this Journal
Abstract
"Scaling" plays an important role for safety analyses in the licensing of water cooled nuclear power reactors. Accident analyses, a sub set of safety analyses, is mostly based on nuclear reactor system thermal hydraulics, and therefore based on an adequate experimental data base, and in recent licensing applications, on best estimate computer code calculations. In the field of nuclear reactor technology, only a small set of the needed experiments can be executed at a nuclear power plant; the major part of experiments, either because of economics or because of safety concerns, has to be executed at reduced scale facilities. How to address the scaling issue has been the subject of numerous investigations in the past few decades (a lot of work has been performed in the 80thies and 90thies of the last century), and is still the focus of many scientific studies. The present paper proposes a "roadmap" to scaling. Key elements are the "scaling-pyramid", related "scaling bridges" and a logical path across scaling achievements (which constitute the "scaling puzzle"). The objective is addressing the scaling issue when demonstrating the applicability of the system codes, the "key-to-scaling", in the licensing process of a nuclear power plant. The proposed "road map to scaling" aims at solving the "scaling puzzle", by introducing a unified approach to the problem.
Keywords
Licensing; Scaling; System Thermal Hydraulics; Best Estimate Plus Uncertainty; Safety Analysis;
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  • Reference
1 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)
2 S. Yokobori, H. Nakamura, "Optimized apportion between large-scale nuclear thermal-hydraulic tests and simulation". JAE 27, pp. 461-468 (in Japanese).(2008)
3 N.E. Todreas, M.S. Kazimi, "Nuclear Systems". Hemisphere Publishing Corp.(1990)
4 L.S. Tong, J.Weisman, J., "Thermal Analysis of Pressurized Water Reactors". ANS La Grange Park, USA (1996).
5 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)
6 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)   DOI
7 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)   DOI
8 N. Zuber, "The effects of complexity, of simplicity and of scaling in thermalhydraulics", Nuclear Engineering and Design, 204, pp. 1-27 (2001).   DOI
9 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)
10 Special Issue devoted to Scaling, Nuclear Engineering and Design 186, (1998)
11 A.N. Navahandi, S. Castellana and E.N. Moradkhaniav, "Scaling laws for modeling nuclear reactor systems" Nuclear Science and Engineering, 72 (1982)
12 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)
13 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)
14 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)
15 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).
16 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)
17 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)   DOI
18 E. Buckingham,"On physically similar systems; illustrations of the use of dimensional equations." Phys. Rev. 4, pp.345-376 (1914).   DOI
19 F. D'Auria and G. M. Galassi, "Scaling in Nuclear Reactor System Thermal Hydraulics", Nuclear Engineering and Design, 240, pp. 3266-3293 (2010)
20 Special Issuedevoted to CSAU, Nuclear Engineering and Design, 119-1, (1990)
21 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)
22 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)
23 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)   DOI