Thermal-hydraulic modeling of reactivity accidents in MTR reactors

References

1IAEA: Research Reactor Core Conversion from the use of Highly Enriched Uranium to the use of Low Enriched Uranium Fuels. Guidebook. TECDOC 233, TECDOC 643, 1980Search in Google Scholar

2Woodruff, W. L.: A kinetic and thermal-hydraulic capability for the analysis of research reactors. Nuclear Technology64 (1984) 196Search in Google Scholar

3Mirza, A. M.; Khanan, S.; Mirza, N. M.: Simulation of reactivity transient current MTRS. Annals of Nuclear Energy25 (1998) 146510.1016/S0306-4549(98)00020-6Search in Google Scholar

4Nasir, R.; Mirza, N. M.; Mirza, S. M.: Sencitivity of reactivity insertion limits with respect to safety parameters in a typical MTR. Annals of Nuclear Energy26 (1999) 1517Search in Google Scholar

5Housiadas, C.: Simulation of Loss of Flow transients in research reactors. Annals of Nuclear Energy27 (2000) 168310.1016/S0306-4549(00)00053-0Search in Google Scholar

6Sanchez, J.: On the Numerical Solution of the Point Reactor Kinetics Equations by Generalized Runge-Kutta Methods. Nuclear Science and Engineering103 (1989) 94Search in Google Scholar

7Housiadas, C.: Lumped parameter analysis of coupled kinetics and thermal-hydraulic for small reactor. Annals of Nuclear Energy29 (2002) 1315Search in Google Scholar

8Meyer, J. E.: Hydrodynamic models for the treatment of reactor thermal transients. Nuclear Science and Engineering10 (1961) 269Search in Google Scholar

9Obenchin, C. F.: PARET-A Program for the Analysis of Reactor Transients. ACE Research and Development Report, IDO-17282, 1969Search in Google Scholar

10Lax, P.; Wendroff, B.: Systems of Conservation Laws. Comm. On Pure and Appl. Math.13 (1960) 21710.1002/cpa.3160130205Search in Google Scholar

11Collier, J. G.; Thome, J. R.: Convective Boiling and Condensation. Oxford Science Publications, Third Edition, 1996Search in Google Scholar

12Rohsenow, W. M.; Choi, H. Y.: Heat, mass, momentum transfer. Prentice-Hall, Inc.Englewood Cliffs, N. J. (1961)Search in Google Scholar

13NobuakiOhnishi; KiyomiIshijima; SadanitsuTanzawa: A Study of Subcooled Film-Boiling Under Reactivity-Initiated Accident Conditions in Light Water Reactors. Nuclear Science and Engineering88 (1984) 33110.13182/NSE84-A18587Search in Google Scholar

14Tong, L. S.; Currin, H. B.: DNB (Burnout) Studies in an Open Lattice Core. USAEC Report WCAP-3736 (1964)Search in Google Scholar

15Dougal, R. S.; Rohsenow, W. M.: Film Boiling on the Inside of Vertical Tubes with Upward Flow of the Fluid at Low Qualities. MIT Report 9079–26 (1963)Search in Google Scholar

16McDoough, J. B.; Milich, E.; King, E. C.: An Experimental Study of Partial Film Boiling Region with water at Elevated Pressure in a Round Vertical Tube. A.I.Ch.E Preprint No. 29, Fourth National Heat Transfer Confernce (1960)Search in Google Scholar

17Bernath, L.: A Theory of Local-Boiling Burnout and its Application to Existing Data. Chem. Eng. Prog., Symp. SER.56 (1960) 95–116Search in Google Scholar

18Munoz-Cobo, J. L.; Chiva, S.; Sekhri, A.: A reduced order model of BWR dynamics with subcooled boiling and modal kinetics: application to out of phase oscillations. Annals of Nuclear Energy31 (2004) 1135Search in Google Scholar

19Zuber, N.; Stube, F. W.; Bijwaard, G.: Vapor Void Fraction in Sub cooled Boiling and in Saturated Boiling Systems: From Proceedings of the Third International Heat Transfer Conference, Chicago, Illinois, August 7 to 12, 1966, New York: American Institute of Chemical Engineering, Volume V, 1966, 24–38Search in Google Scholar

20Kuo-FuChen: Effect of System Pressure On Reactor Power Limits Criteria: Nuclear Reactor Safety, July 14, 1992Search in Google Scholar

21ETRR-2: Egypt Second Reactor Safety Analysis Report (SAR), 1998Search in Google Scholar