An object-oriented approach to simulation of IRIS dynamic response

Progress in Nuclear Energy

Volumn 53, Issue 1, 2011, Pages 48-58

  Cammi, Antonio ^a   Casella, Francesco ^a   Ricotti, Marco E ^a   Schiavo, Francesco ^a  

^a POLITECNICO DI MILANO   (Italy)

Author keywords

Control; Integral reactors; Modelling; Object oriented; Simulation

Indexed keywords

BALANCE OF PLANT; CODE VALIDATION; COMPONENT MODEL; DYNAMIC SIMULATION; DYNAMIC SYSTEMS; DYNAMICS AND CONTROL; INDUSTRIAL FIELDS; INTEGRAL REACTORS; INTERNATIONAL CONSORTIUM; INTERNATIONAL REACTOR INNOVATIVE AND SECURE; KEY FEATURE; LICENSING PROCESS; LIGHT WATER; MODELICA; MODELICA LANGUAGE; MODELLING; MODELLING AND SIMULATIONS; MODULAR APPROACH; MULTI-PHYSICS; NUCLEAR MODEL; NUCLEAR POWER GENERATION; NUCLEAR REGULATORY COMMISSION; OBJECT ORIENTED; OBJECT ORIENTED APPROACH; OPEN-SOURCE; POINT REACTOR KINETICS; POWER GENERATION PLANTS; PRELIMINARY DESIGN; REACTOR DYNAMICS; REACTOR REACTORS; SIMULATION; SIMULATION CODE; SIMULATION TOOL; SYSTEM MODELS; SYSTEM SIMULATOR; TOOL SUPPORT;

COMPUTER SOFTWARE; CONTROL RODS; DYNAMIC RESPONSE; ELECTRIC CONVERTERS; EQUIPMENT TESTING; NUCLEAR ENERGY; NUCLEAR PROPULSION; PRESSURIZED WATER REACTORS; REACTOR SHUTDOWNS; SIMULATORS; TOOLS;

OBJECT ORIENTED PROGRAMMING;

EID: 78249244151     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.pnucene.2010.09.004     Document Type: Article

References (35)

1. E. Brega, C. Lombardi, M.E. Ricotti, and R. Sordi Development and initial validation of fast-running simulator of PWRs: TRAP-2 IAEA-TECDOC-872 1996 IAEA Vienna 341 352
2. K.E. Brenan, S.L. Campbell, and L.R. Petzold Numerical Solution of Initial-value Problems in Differential Algebraic Equations 1989 North-Holland Ed
3. A. Cammi, F. Casella, M.E. Ricotti, F. Schiavo, and G.D. Storrick Object-oriented simulation for the control of the IRIS nuclear power plant Proceedings 16th IFAC World Congress, Prague, Czech Republic, Jul. 3-8 2005
4. A. Cammi, F. Casella, M.E. Ricotti, and Schiavo Object-oriented modeling, simulation and control of the IRIS nuclear power plant with modelica Proceedings 4th International Modelica Conference, Hamburg, Germany, Mar. 7-8 2005 423 432
5. M.D. Carelli, L.E. Conway, C.L. Kling, L. Oriani, B. Petrovic, C.V. Lombardi, M.E. Ricotti, A.C.O. Barroso, J.M. Collado, L. Cinotti, N.E. Todreas, D. Grgic, R.D. Boroughs, H. Ninokata, and F. Oriolo Design and safety of IRIS, an integral water cooled SMR for near term deployment V. Kuznetsov, Innovative Small and Medium Sized Reactors: Design Features, Safety Approaches and R&D Trends. IAEA-TECDOC-1451 2005 IAEA Vienna 51 74
6. M.D. Carelli, L.E. Conway, L. Oriani, B. Petrovic, C.V. Lombardi, M.E. Ricotti, A.C.O. Barroso, J.M. Collado, L. Cinotti, N.E. Todreas, D. Grgic, M.M. Moraes, R.D. Boroughs, H. Ninokata, D.T. Ingersoll, and F. Oriolo The design and safety features of the IRIS reactor Nuclear Engineering and Design 230 2004 151 167
7. K.E. Carlson, V.T. Berta, C.E. Lenglade, R.A. Riemke, M.A. Lintner, R.R. Schultz, C.D. Fletcher, C.C. McKenzie, A.S.-L. Shieh, E.E. Jenkins, G.L. Mesina, R.W. Shumway, E.C. Johnsen, C.S. Miller, C.E. Slater, G.W. Johnsen, G.A. Mortensen, S.M. Sloan, J.M. Kelly, P.E. Murray, M. Warnick, H.-H. Kuo, R.B. Nielson, W.L. Weaver, N.S. Larson, S. Paik, and G.E. Wilson RELAP5/MOD3 code manual. NUREG/CR-5535, INEL-95/0174 vol. I-IV 1990 Rev. 1
8. F. Casella Object-oriented modelling of two-phase fluid flows by the finite volume method Proceedings 5th Mathmod Vienna, Austria, Sep. 6-8 2006 631 640
9. F. Casella, and A. Leva Modelica open library for power plant simulation: design and experimental validation Proceedings of Modelica Conference 2003, Linköping, Sweden, Nov. 3-4 2003 41 50 http://www.modelica.org/ Conference2003/papers/h08-Leva.pdf
10. F. Casella, and A. Leva Modelling of thermo-hydraulic power generation processes using modelica Mathematical and Computer Modeling of Dynamical Systems 12 1 2006 19 33
11. A. Cioncolini, A. Cammi, L. Cinotti, G. Castelli, C. Lombardi, L. Luzzi, and M.E. Ricotti Thermal hydraulic analysis of iris reactor coiled tube steam generator ANS Topical Meeting in Mathematics & Computations (M&C), April 6-10, Gatlinburg, TN, USA 2003
12. L.E. Conway, B. Petrovic, T. Kanagawa, and M.E. Ricotti Internal control rod drive mechanism, design options for IRIS Proceedings of ICAPP'04, Paper 4315, Pittsburgh, June 13-17 2004
13. Dymola Dymola User's Manual 2008 DynasymAB
14. P. Fritzson, Proceedings of the 2003 Modelica Conference, Linköping, Sweden, Nov. 3-4 2003 http://www.modelica.org/events/Conference2003
15. P. Fritzson Principles of Object-oriented Modeling and Simulation with Modelica 2.1 2004 Wiley-IEEE Press
16. M.V.I. Fukami, and A. Santecchia CAREM project: innovative small PWR Progress in Nuclear Energy 37 1-4 2000 265 270
17. D. Grgic, T. Bajs, and L. Oriani Development of RELAP5 nodalization for IRIS non-loca transient analyses Proceedings of ANS Topical Meeting in Mathematics & Computations, Gatlinburg, USA, April 6-10 2003
18. C. Kral, Proceedings of the 2006 Modelica Conference, Vienna, Austria, Sep. 4-5 2006 http://www.modelica.org/events/modelica2006/Proceedings/
19. G. Lerchl, and H. Austregesilo The ATHLET code documentation package User's Manual, GRS-P-1 Vol. 1 1995
20. D.R. Liles, and J.H. Mahassi TRAC-PF1/MOD1: An Advanced Best Estimate Computer Program For Pressurized Water Reactor Thermal Analysis 1986 NUREG/CR-3858
21. MathModelica MathModelica User's Manual 2008 Mathcore Engineering AB
22. S.E. Mattsson, H. Elmqvist, and M. Otter Physical system modeling with modelica Control Engineering Practice 6 1998 501 510
23. J.C. Micaelli, D. Bestion, M. Bernard, A. Porracchia, J.M. Miraucourt, and L. Catalani CATHARE. Best estimate thermal hydraulic code for reactor safety studies, last developments Proceedings of the International ENS/ANS Conference on Thermal Reactor Safety, Avignon, October 2-7 1988
24. Modelica Association web site http://www.modelica.org/ 2007
25. OpenModelica Open Modelica project http://www.ida.liu.se/labs/pelab/ modelica/OpenModelica.html 2008
26. M. Otter, Proceedings of the 2002 Modelica Conference, Oberpfaffenhofen, Germany, March, 18-19 2002 http://www.modelica.org/Conference2002/papers.shtml
27. E. Popov, and G. Yoder IRIS pressurizer fluid dynamics and heat transfer analyses Nuclear Engineering and Design 238 2008 81 89
28. M.E. Ricotti, A. Cammi, M. Carelli, E. Colombo, C. Lombardi, M. Passoni, and C. Rizzo Hydraulically driven control rod concept for integral reactors: fluid dynamic simulation and preliminary test Proceedings of GENES4/ANP2003, Paper 1028, Kyoto, Sept. 15-19 2003
29. F. Schiavo, and F. Casella Object-oriented modelling and simulation of heat exchangers with finite element methods Mathematical and Computer Modelling of Dynamical Systems 13 3 2007 211 235
30. G. Schmitz, Proceedings of the 2005 Modelica Conference, Hamburg, Germany, March 7-8 2005 http://www.modelica.org/events/Conference2005
31. Thermo Power Home Page http://home.dei.polimi.it/casella/thermopower/ 2008
32. N. Todreas, and M. Kazimi Nuclear Systems I & II 2001 Taylor & Francis Education USA
33. Vitulo, A., 2003. Development of the Internal Hydraulically Driven Control Rod Concept for the IRIS reactor. Master thesis, Politecnico di Milano.
34. W. Wagner, J.R. Cooper, A. Dittmann, J. Kijima, H.J. Kretzschmar, A. Kruse, R. Mareš, K. Oguchi, H. Sato, I. Stöcker, O. Šifner, Y. Takaishi, I. Tanishita, J. Trübenbach, and T. Willkommenet The IAPWS industrial formulation 1997 for the thermodynamic properties of water and steam ASME Journal of Engineering for Gas Turbines and Power 122 2000 150 182
35. L. Xiaotian, and H. Shuyan Dynamic behavior of upper hydraulic drive control rod Nuclear Engineering and Design 236 2006 2556 2566