An approach for the modelling and the analysis of the MSR thermo-hydrodynamic behaviour

Chemical Engineering Science

Volumn 65, Issue 16, 2010, Pages 4873-4883

  Luzzi, Lelio ^a   Cammi, Antonio ^a   Di Marcello, Valentino ^a   Fiorina, Carlo ^a  

^a POLITECNICO DI MILANO   (Italy)

Author keywords

Circulating fuel reactor; Computational fluid dynamics; Heat transfer; Internally heat generating fluid; Molten salt reactor; Turbulence

Indexed keywords

A-THERMAL; ANALYTIC APPROACH; ANALYTIC SOLUTION; CIRCULAR PIPE; CIRCULATING FUEL REACTOR; DYNAMIC BEHAVIOURS; FINITE VOLUME; FISSILE MATERIALS; FLUID VELOCITIES; FUEL REACTORS; GENERATION IV; GRAPHITE MATRIX; GRAPHITE-MODERATED; HEAT TRANSFER CHARACTERISTICS; HIGH TEMPERATURE MOLTEN SALTS; IN-PIPE; INNOVATIVE NUCLEAR REACTOR; INTERNAL HEAT GENERATION; INTERNAL HEAT SOURCE; KEY ISSUES; LIQUID NUCLEAR FUEL; MOLTEN HALIDES; MOLTEN SALT; MOLTEN SALT REACTOR; MULTI-PHYSICS; MULTIPHYSICS SIMULATIONS; NEUTRON MODERATORS; NEUTRONICS; NUCLEAR APPLICATION; NUMERICAL COMPUTATIONS; NUMERICAL SOLUTION; PHYSICAL PHENOMENA; PRELIMINARY ASSESSMENT; RAPID GROWTH; RESEARCH AND DEVELOPMENT; TEMPERATURE FIELD; THERMAL HYDRAULICS; THERMOHYDRODYNAMICS;

COMPUTER SOFTWARE; FLUID DYNAMICS; FLUIDS; FUELS; FUSED SALTS; GRAPHITE; HEAT EXCHANGERS; HEAT GENERATION; HIGH TEMPERATURE APPLICATIONS; HYDRODYNAMICS; KNOWLEDGE BASED SYSTEMS; LINEAR SYSTEMS; MOLTEN MATERIALS; NUCLEAR ENERGY; NUCLEAR PROPULSION; NUCLEAR REACTORS; NUMERICAL ANALYSIS; NUSSELT NUMBER; PILE FOUNDATIONS; PIPE; PIPE FLOW; REYNOLDS NUMBER; TURBULENCE;

COMPUTATIONAL FLUID DYNAMICS;

EID: 77954386708     PISSN: 00092509     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.ces.2010.05.040     Document Type: Article

References (67)

1. Abram T., Ion S. Generation-IV nuclear power: a review of the state of the science. Energy Policy 2009, 36:4323-4330.
2. Ambrosek J., Anderson M., Sridharan K., Allen T. Current status of knowledge of the fluoride salt (FLiNaK) heat transfer. Nuclear Technology 2009, 165(2):166-173.
3. Bin L., Yu-ting W., Chong-fang M., Meng Y., Hang G. Turbulent convective heat transfer with molten salt in a circular pipe. International Communications in Heat and Mass Transfer 2009, 36:912-916.
4. Bird R.B., Stewart W.E., Lightfoot E.N. Transport Phenomena 1960, Wiley, New York.
5. Boussinesq J.V. Essai sur la théorie des eaux courantes. Mémoires Présentés par Divers Savants à l'Académie des Sciences 1877, 23(24):1-680.
6. 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., 2009.
7. Cammi, A., Di Marcello, V., Luzzi, L., 2007. Modelling of circulating nuclear fuels with COMSOL Multiphysics. In: Proceedings of the European COMSOL Conference 2007, Grenoble, France, vol. 1, pp. 380-386, COMSOL, Inc., 2007.
8. Cammi A., Luzzi L. Innovative techniques for the simulation and control of nuclear power plants. Energy Conversion: New Research 2008, 1-4. Nova Science Publishers, Hauppauge NY. W. Lín (Ed.).
9. Cammi, A., Di Marcello, V., Luzzi, L., Memoli, V., unpublished results. A multi-physics modelling approach to the dynamics of molten salt reactors. Annals of Nuclear Energy, Submitted.
10. Carslaw H.S., Jaeger J.C. Conduction of Heat in Solids 1959, Oxford University Press, London.
11. Churchill S.W. New simplified models and formulations for turbulent flow and convection. A.I.Ch.E. Journal 1997, 43(5):1125-1140.
12. Colburn A.P. A method of correlating forced convection heat transfer data and a comparison with fluid friction. Transactions of the A.I.Ch.E. 1933, 29:174-210.
13. COMSOL Multiphysics® 3.5a User's Guide, COMSOL Inc., 2008.
14. Di Marcello, V., 2009. A multi-physics approach to the modelling of the molten salt reactor. In: Proceedings of the Second International Youth Conference on Energetics 2009, Budapest, Hungary.
15. Di Marcello, V., Cammi, A., Luzzi, L., 2008a. Analysis of coupled dynamics of molten salt reactors. In: Proceedings of the European COMSOL Conference 2008, Hannover, Germany, CD-ROM, COMSOL Inc., 2008.
16. Di Marcello, V., Cammi, A., Luzzi, L., 2008b. 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. Di Marcello V., Cammi A., Luzzi L. A generalized approach to heat transfer in pipe flow with internal heat generation. Chemical Engineering Science 2010, 65:1301-1310.
18. Dittus F.W., Boelter L.M.K. Heat Transfer in Automobile Radiators of the Tubular Type 1930, 2. University of California publications in Engineering, 443-461.
19. Duderstadt J.J., Hamilton L.J. Nuclear Reactor Analysis 1975, John Wiley & Sons, New York.
20. Ferri R., Cammi A., Mazzei D. Molten salt mixture properties in RELAP5 code for thermodynamic solar applications. International Journal of Thermal Sciences 2008, 47(12):1676-1687.
21. Fiorina, C., 2009. A generalized approach to assess the COMSOL® capabilities for the analysis of the MSR thermo-fluid dynamics. M.Sc. Thesis, Politecnico di Milano, Milano, Italy.
22. FLUENT® 6.2 User's Guide, Fluent Inc., 2005.
23. Forsberg C.W., Peterson P.F., Pickard P.S. Molten-salt-cooled advanced high-temperature reactor for production of hydrogen and electricity. Nuclear Technology 2003, 144:289-302.
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 Seventh International Congress on Advances in Nuclear Power Plants (ICAPP '07), Nice, France.
25. 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.
26. Generation IV International Forum, 2008. Gen IV International Forum 2008 Annual Report.
27. Gil A., Medrano M., Martorell I., La'zaro A., Dolado P., Zalba B., Cabeza L.F. State of the art on high temperature thermal energy storage for power generation. Part 1-concepts, materials and modellization. Renewable and Sustainable Energy Reviews 2010, 14:31-55.
28. Gnielinski V. New equations for heat and mass transfer in turbulent pipe and channel flow. International Chemical Engineering 1976, 16(2):359-367.
29. Graetz L. Über die Wärmeleitungsfähigkeit von Flüssigkeiten, part I. Annalen der Physik und Chemie 1883, 18:79-94.
30. Graetz L. Über die Wärmeleitungsfähigkeit von Flüssigkeiten, Part II. Annalen der Physik und Chemie 1885, 25:337-357.
31. Guo J., Julien P.Y. Modified log-wake law for turbulent flow in smooth pipes. Journal of Hydraulic Research 2003, 41(5):493-501.
32. Haubenreich, P.N., Engel, J.R., 1962. Temperatures in the MSRE core during steady-state power operation. Technical report, ORNL-TM-0378.
33. Hausen H. Neue Gleichungen für die wärmeübertragung bei freier oder erzwungener Stromüng (new equations for heat transfer in free or forced flow). Allgemein Wärmetechnik 1959, 9(4/5):75-79.
34. Hejzlar P., Todreas N.E., Shwageraus E., Nikiforova A., Petroski R., Driscoll M.J. Cross-comparison of fast reactor concepts with various coolants. Nuclear Engineering and Design 2009, 239:2672-2691.
35. Hron, M., Uhlìr, J., Renault, C., 2006. "Molten Salt Reactor" Current status and future prospects within European activities (MSR). In: Proceedings of the FISA 2006-Conference on EU Research and Training in Reactor Systems, Luxembourg, 2006, pp. 270-286.
36. Hsu C. Exact solution to entry-region laminar heat transfer with axial heat conduction and the boundary condition of the third kind. Chemical Engineering Science 1968, 23(5):457-468.
37. Incropera F.P., DeWitt D.P., Bergman T.L., Lavine A. Fundamentals of Heat and Mass Transfer 2006, John Wiley and Sons, Hoboken, New Jersey.
38. Jischa M., Rieke H.B. About the prediction of turbulent Prandtl and Schmidt numbers from modified transport equations. International Journal of Heat and Mass Transfer 1979, 22(11):1547-1555.
39. Kasten, P.R., 1969. Graphite behavior and its effects on MSBR performance. Technical report, ORNL-TM-2136.
40. Khokhlov V., Ignatiev V., Afonichkin V. Evaluating physical properties of molten salt reactor fluoride mixtures. Journal of Fluorine Chemistry 2009, 130:30-37.
41. Kópházi J., Lathouwers D., Kloosterman J.L. 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. Nuclear Science and Engineering 2009, 163:118-131.
42. Korea Atomic Energy Research Institute, http://atom.kaeri.re.kr/.
43. Křepel J., Rohde U., Grundmann U., Weiss F.P. DYN3D-MSR spatial dynamics code for molten salt reactors. Annals of Nuclear Energy 2007, 34:449-462.
44. 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.
45. 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.
46. Mathieu L., Heuer D., Brissot R., Garzenne C., Le Brun C., Lecarpentier D., Liatard E., Loiseaux J.M., Me'plan O. The thorium molten salt reactor: moving on from the MSBR. Progress in Nuclear Energy 2006, 48:664-679.
47. MATLAB 6.5 User's Guide, The MathWorks Inc., 2002.
48. 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., 2009.
49. Mikhailov M.D., Ozişik M.N Unified Analysis and Solutions of Heat and Mass Diffusion 1984, Dover Publications Inc., New York.
50. Moriyama H., Sagara A., Tanaka S., Moir R.W., Sze D.K. Molten salt in fusion nuclear technology. Fusion Engineering and Design 1998, 39-40:627-637.
51. Nicolino C., Lapenta G., Dulla S., Ravetto P. Coupled dynamics in the physics of molten salt reactors. Annals of Nuclear Energy 2008, 35:314-322.
52. OECD/NEA, 2007. Handbook on lead-bismuth eutectic alloy and lead properties, materials compatibility, thermal-hydraulics and technologies. Technical report NEA no. 6195.
53. Petukhov, B.S., 1970. Heat transfer and friction in turbulent pipe flow with variable physical properties. In: Advances in Heat Transfer, Academic, New York, pp. 504-564.
54. Poppendiek, H.F., 1954. Forced-convection heat transfer in pipes with volume-heat sources within the fluids. In: Chemical Engineering Progress Symposium Series, vol. 50, no. 11, pp. 93-104.
55. 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.
56. Robertson, R.C., 1971. Conceptual design study of a single-fluid molten-salt breeder reactor. Technical report, ORNL-4541.
57. Rosenthal, M.W., Briggs, R.B., Kasten, P.R., 1969. Molten salt reactor program semiannual progress report. Technical report, ORNL-4396.
58. Rosenthal M.W., Kasten P.R., Briggs R.B. Molten-salt reactors-history, status, and potential. Nuclear Applications and Technology 1970, 8:107-117.
59. Sieder E.N., Tate G.E. Heat transfer and pressure drop of liquids in tubes. Industrial and Engineering Chemistry 1936, 28(12):1429-1435.
60. Todreas N.E., Kazimi M.S. Nuclear Systems. I. Thermal Hydraulic Fundamentals 1990, Hemisphere Publishing Corporation, New York.
61. Weigand B., Kanzamar M., Beer H. The extended Graetz problem with piecewise constant wall heat flux for pipe and channel flows. International Journal of Heat and Mass Transfer 2001, 44(20):3941-3952.
62. Wilcox D.C. Turbulence Modeling for CFD 2006, DCW Industries, Inc., La Cañada, California.
63. Williams D.F., Clarno K.T. Evaluation of salt coolants for reactor applications. Nuclear Technology 2008, 163:330-343.
64. Yamamoto T., Mitachi K., Suzuki T. Steady state analysis of small molten salt reactor. JSME International Journal 2005, 48(3):610-717.
65. Yu B., Ozoe H., Churchill S.W. The characteristic of fully developed turbulent convection in a round tube. Chemical Engineering Science 2001, 56(5):1781-1800.
66. Yu-ting W., Bin L., Chong-fang M., Meng Y., Hang G. Convective heat transfer in the laminar-turbulent transition region with molten salt in a circular tube. Experimental Thermal and Fluid Science 2009, 33:1128-1132.
67. Zagarola M.V., Smits A.J. Scaling of the mean velocity profile for turbulent pipe flow. Physical Review Letters 1997, 78(2):239-242.