A multi-physics modelling approach to the dynamics of Molten Salt Reactors

Annals of Nuclear Energy

Volumn 38, Issue 6, 2011, Pages 1356-1372

  Cammi, Antonio ^a   Di Marcello, Valentino ^a,b   Luzzi, Lelio ^a   Memoli, Vito ^a   Ricotti, Marco Enrico ^a  

^a POLITECNICO DI MILANO   (Italy)

^b JOINT RESEARCH CENTRE   (Italy)

Author keywords

Molten Salt Reactor; Multi physics modelling; Reactor dynamics; Thermo hydrodynamics

Indexed keywords

CONVENTIONAL APPROACH; DELAYED NEUTRON PRECURSOR; DIFFUSION THEORY; ENERGY BALANCE EQUATIONS; FUEL MASS; GENERATION IV; GROUP CONSTANT; MOLTEN SALT; MOLTEN SALT REACTOR; MULTI-PHYSICS; NEUTRON TRANSPORT; NEUTRONICS; PERIODIC PERTURBATION; PHYSICAL QUANTITIES; REACTIVITY INSERTION; REACTOR DYNAMICS; REYNOLDS-AVERAGED NAVIER-STOKES; SIMULATION ENVIRONMENT; SPATIAL EFFECT; STEADY-STATE CONDITION; TEMPERATURE FEEDBACK; THERMOHYDRODYNAMICS; TIME CONSTANTS; WORKING CONDITIONS;

BEHAVIORAL RESEARCH; FLUID DYNAMICS; FUELS; FUSED SALTS; GRAPHITE; HEAT TRANSFER; HYDRODYNAMICS; MOLTEN MATERIALS; NEUTRON FLUX; NUCLEAR POWER PLANTS; NUCLEAR REACTORS;

NAVIER STOKES EQUATIONS;

EID: 79953742937     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2011.01.037     Document Type: Article

References (61)

1. G.I. Bell, and S. Glasstone Nuclear Reactor Theory 1970 Van Nostrand Reinhold Co. New York
2. E.S. Bettis, R.W. Schroeder, and G.A. Cristy The aircraft reactor experiment - design and construction Nucl. Sci. Eng. 2 1957 804 825
3. Bowman, S.M., Dunn, M.E., Hollenbach, D.F., Jordan, W.C., 2005. Scale Cross Section Libraries. Technical Report, ORNL/TM-2005/39.
4. Briesmeister, J.F., 2000. MCNP - A General Monte Carlo N-Particle Transport Code. Technical Report, LA-13709-M, Los Alamos National Laboratory.
5. Cammi, A., Di Marcello, V., Fiorina, C., Luzzi, L., 2009. Assessment of COMSOL capabilities to analyse the thermo-hydrodynamic behaviour of the MSR core. In: Proceedings of the COMSOL Conference 2009, Milan, Italy, CD-ROM, COMSOL, Inc.
6. A. Cammi, V. Di Marcello, and L. Luzzi Modelling of circulating nuclear fuels with COMSOL Multiphysics Proceedings of the European COMSOL Conference 2007, Grenoble, France vol. 1 2007 COMSOL, Inc. Berlin 380 386
7. A. Cammi, and L. Luzzi Innovative techniques for the simulation and control of nuclear power plants V.B. Durelle, Nuclear Energy Research Progress 2008 Nova Science Publishers 1 4
8. S.W. Churchill New simplified models and formulations for turbulent flow and convection AIChE J. 43 5 1997 1125 1140
9. S.W. Churchill A reinterpretation of the turbulent Prandtl number Ind. Eng. Chem. Res 41 25 2002 6393 6401 (Pubitemid 35429830)
10. COMSOL Multiphysics® 3.5a USER'S Guide, 2008a. COMSOL Inc.
11. COMSOL Multiphysics® 3.5a Reference Guide, 2008b. COMSOL Inc.
12. T.A. Davis Algorithm 832: UMFPACK, an unsymmetric-pattern multifrontal method ACM Trans. Math. Software 30 2 2004 196 199
13. DeHart, M.D., 2005a. TRITON: A Two-dimensional Depletion Sequence for Characterization of Spent Nuclear Fuel. Technical Report, ORNL/TM-2005/39.
14. DeHart, M.D., 2005b. NEWT: A New Transport Algorithm for Two-dimensional Discrete Ordinates Analysis in Non-orthogonal Geometries. Technical Report, ORNL/TM-2005/39.
15. Di Marcello, V., 2010. Development of a Multi-physics Approach to the Modelling and Analysis of Molten Salt Reactors. Ph.D. Thesis, Politecnico di Milano.
16. Di Marcello, V., Cammi, A., Luzzi, L., 2008. Analysis of thermal-hydraulic behaviour of the molten salt nuclear fuel. In: Proceedings of the International Conference Nuclear Energy for New Europe 2008, Portorož, Slovenia, pp. 301.1-301.10.
17. V. Di Marcello, A. Cammi, and L. Luzzi A generalized approach to heat transfer in pipe flow with internal heat generation Chem. Eng. Sci. 65 2010 1301 1310
18. S. Dulla, and C. Nicolino Dynamics of fluid fuel reactors in the presence of periodic perturbations Sci. Technol. Nucl. Instal. 2008 2008 1 11
19. S. Dulla, and P. Ravetto Interactions between fluid-dynamics and neutronics phenomena in the physics of molten-salt systems Nucl. Sci. Eng. 155 2007 475 488 (Pubitemid 46411700)
20. S. Dulla, P. Ravetto, and M.M. Rostagno Neutron kinetics of fluid-fuel systems by the quasi-static method Ann. Nucl. Energy 31 2004 1709 1733
21. Energy from Thorium. Documents Related to Liquid-halide (Fluoride and Chloride) Reactor Research and Development. In: .
22. FLUENT® 6.2 User's Guide, 2005. Fluent Inc.
23. C.W. Forsberg, P.F. Peterson, and P.S. Pickard Molten-salt-cooled advanced high-temperature reactor for production of hydrogen and electricity Nucl. Technol. 144 2003 289 302
24. Forsberg, C., Renault, C., Le Brun, C., Merlet-Lucotte, E., Ignatiev, V., 2007. Liquid salt applications and molten salt reactors. In: Proceedings of the 7th International Congress on Advances in Nuclear Power Plants (ICAPP '07), Nice, France.
25. K. Furukawa, K. Arakawa, L.B. Erbay, Y. Ito, Y. Kato, H. Kiyavitskaya, A. Lecocq, K. Mitachi, R. Moir, H. Numata, J.P. Pleasant, Y. Sato, Y. Shimazu, V.A. Simonenco, D.D. Sood, C. Urban, and R. Yoshioka A road map for the realization of global-scale thorium breeding fuel cycle by single molten-fluoride flow Energy Convers. Manage. 49 2008 1848 1932
26. Generation IV International Forum, 2002. A Technology Road Map for Generation IV Nuclear Energy Systems, GIF-002-00. Issued by the US DOE Nuclear Energy Research Advisory Committee and The Generation IV International Forum.
27. Generation IV International Forum, 2008. Gen IV International Forum 2008 Annual Report.
28. P. Hejzlar, N.E. Todreas, E. Shwageraus, A. Nikiforova, R. Petroski, and M.J. Driscoll Cross-comparison of fast reactor concepts with various coolants Nucl. Eng. Des. 239 2009 2672 2691
29. Hron, M., Uhlr, J., Renault, C., 2006. "Molten salt reactor" current status and future prospects within European activities (MSR). In: Proceedings of FISA 2006 - Conference on EU Research and Training in Reactor Systems, Luxembourg, 2006, pp. 270-286.
30. M. Jischa, and H.B. Rieke About the prediction of turbulent Prandtl and Schmidt numbers from modified transport equations Int. J. Heat Mass Transfer 22 11 1979 1547 1555 (Pubitemid 10478060)
31. J. Kópházi, D. Lathouwers, and J.L. Kloosterman Development of a three-dimensional time-dependent calculation scheme for molten salt reactors and validation of the measurement data of the molten salt reactor experiment Nucl. Sci. Eng. 163 2009 118 131
32. U. Křepel, J. Grundmann, U. Rohde, and F.P. Weiss DYN1D-MSR dynamics code for molten salt reactors Ann. Nucl. Energy 32 2005 1799 1824 (Pubitemid 41570144)
33. J. Křepel, U. Rohde, U. Grundmann, and F.P. Weiss DYN3D-MSR spatial dynamics code for molten salt reactors Ann. Nucl. Energy 34 2007 449 462 (Pubitemid 46754658)
34. J. Křepel, U. Rohde, U. Grundmann, and F.P. Weiss Dynamics of molten salt re actors Nucl. Technol. 164 2008 34 44
35. J.R. Lamarsh Introduction to Nuclear Reactor Theory 1966 Addison-Wesley Publishing Company Inc. Reading, Massachusetts
36. Lapenta, G., 2005. Mathematical and numerical models for the coupling of neutronics and thermal-hydrodynamics in circulating fuel nuclear reactors. In: Nuclear Reactor Physics. CLUT, Turin, pp. 195-210.
37. G. Lapenta, F. Mattioda, and P. Ravetto Point kinetic model for fluid fuel systems Ann. Nucl. Energy 28 2001 1759 1772 (Pubitemid 32780362)
38. LeBlanc, D., 2009. Molten salt reactor: a new beginning for an old idea. In: Proceedings of 17th International Conference on Nuclear Engineering (ICONE17), Brussels, Belgium.
39. D. Lecarpentier, and V. Carpentier A neutronics program for critical and nonequilibrium study of mobile fuel reactors: the Cinsf1D code Nucl. Sci. Eng. 143 2003 33 46
40. E.E. Lewis, and W.F. Miller Computational Methods of Neutron Transport 1984 John Wiley and Sons New York
41. L. Luzzi, A. Cammi, V. Di Marcello, and C. Fiorina An approach for the modelling and the analysis of the MSR thermo-hydrodynamic behaviour Chem. Eng. Sci. 65 2010 4873 4883
42. L. Mathieu, D. Heuer, R. Brissot, C. Garzenne, C. Le Brun, D. Lecarpentier, E. Liatard, J.M. Loiseaux, and O. Méplan The thorium molten salt reactor: moving on from the MSBR Prog. Nucl. Energy 48 2006 664 679 (Pubitemid 44414986)
43. J.L. Meem Two Group Reactor Theory 1964 Gordon and Breach Science Publishers Inc. New York
44. Memoli, V., 2010. Modelling Approaches for Analysis of Innovative Nuclear Reactors. Ph.D. Thesis, Politecnico di Milano.
45. Memoli, V., Cammi, A., Di Marcello, V., Luzzi, L., 2009. A preliminary approach to the neutronics of the molten salt reactor by means of COMSOL Multiphysics. In: Proceedings of the COMSOL Conference 2009, Milan, Italy, CD-ROM, COMSOL, Inc.
46. C. Nicolino, G. Lapenta, S. Dulla, and P. Ravetto Coupled dynamics in the physics of molten salt reactors Ann. Nucl. Energy 35 2008 314 322
47. S.V. Patankar Numerical Heat Transfer and Fluid Flow 1980 Hemisphere Publishing Co. New York
48. Renault, C., Delpech, M., Le Brun, C., Lecarpentier, D., Garzenne, C., Konings, R.J.M., Hosnedl, P., Matal, O., Uhlir, J., 2005. The MOST project: key-points and challenges for the feasibility of molten salt reactors. In: Proceedings of the International Congress Advances Nuclear Power Plants (ICAPP 05), Seoul, South Korea, Paper 5208.
49. Robertson, R.C., 1971. Conceptual Design Study of a Single-fluid Molten-salt Breeder Reactor. Technical Report, ORNL-4541.
50. Rosenthal, M.W., Briggs, R.B., Kasten, P.R., 1970a. Molten-salt Reactor Program Semiannual Progress Report. Technical Report, ORNL-4449.
51. M.W. Rosenthal, P.R. Kasten, and R.B. Briggs Molten-salt reactors - history, status, and potential Nucl. Appl. Technol. 8 1970 107 117
52. A.B. Salah, T. Hamidouche, and F. D'Auria Application of best estimate computational tools for safety accident analysis in nuclear plants W. LÃ-n, Energy Conversion: New Research 2008 Nova Science Publishers Hauppauge, NY (Chapter 4)
53. N. Suzuki, and Y. Shimazu Preliminary safety analysis on depressurization accident without scram of a molten salt reactor J. Nucl. Sci. Technol. 43 2006 720 730 (Pubitemid 44156800)
54. N. Suzuki, and Y. Shimazu Reactivity-initiated-accident analysis without scram of a molten salt reactor J. Nucl. Sci. Technol. 45 2008 575 581
55. J.S. Turner Buoyancy effects in fluids 1973 Cambridge University Press Cambridge
56. S. Wang, A. Rineiski, and W. Maschek Molten salt related extensions of the SIMMER-III code and its application for a burner reactor Nucl. Eng. Des. 236 2006 1580 1588
57. T. Yamamoto, K. Mitachi, K. Ikeuchi, and T. Suzuki Transient characteristics of small molten salt reactor during blockage accident Heat Transfer Asian Res. 35 2006 434 450 (Pubitemid 44426052)
58. T. Yamamoto, K. Mitachi, and T. Suzuki Steady state analysis of small molten salt reactor JSME Int. J. Ser. B 48 3 2005 610 717
59. D.L. Zhang, S.Z. Qiu, G.H. Su, C.L. Liu, and L.B. Qian Analysis on the neutron kinetics for a molten salt reactor Prog. Nucl. Energy 51 2009 624 636
60. D.L. Zhang, S.Z. Qiu, and G.H. Su Development of a safety analysis code for molten salt reactors Nucl. Eng. Des. 239 2009 2778 2785
61. D.L. Zhang, S.Z. Qiu, G.H. Su, and C.L. Liu Development of a steady state analysis code for a molten salt reactor Ann. Nucl. Energy 36 2009 590 603