Experimental and analytical investigation of the ITU TRIGA Mark-II reactor core

T. Büke; H. Yavuz

doi:10.1515/kern-2003-0087

Enjoy 40% off

academic books on De Gruyter Brill *

Article

Experimental and analytical investigation of the ITU TRIGA Mark-II reactor core

T. Büke and H. Yavuz

Published/Copyright: March 16, 2022

Published by

Become an author with De Gruyter Brill

Submit Manuscript Author Information

From the journal Kerntechnik Volume 68 Issue 5-6

Abstract

Experimental and analytical studies have been performed to determine the temperature distribution as a function of reactor power in the TRIGA Mark-II reactor at the Istanbul Technical University (ITU). The lumped parameter model with four governing equations was used in the analytical model. Based on the mathematical model, a computer code has been developed for calculating fuel and coolant temperatures in the reactor core. The calculated results for fuel and coolant temperature in the reactor core for different reactor power levels have been compared with the experimental data. Agreements between experiment and results from the computer code are fairly good.

Abstract

Um die Temperaturverteilung als eine Funktion der Reaktorleistung zu ermitteln, wurden am TRIGA Mark-II Reaktor der Technischen Universität Istanbul (ITU) experimentelle und analytische Studien durchgeführt. In dem analytischen Modell wurde das Blockparametermodell mit vier Hauptgleichungen benutzt. Auf dem mathematischen Modell basierend wurde ein Computercode entwickelt, um die durchschnittliche Temperatur des Brennstoffs und des Kühlmittels im Reaktorkern zu berechnen. Die Ergebnisse der Berechnungen von durchschnittlicher Brennstoff- und Kühlmitteltemperatur im Reaktorkern bei unterschiedlicher Reaktorleistung wurden mit den experimentell ermittelten Daten verglichen. Die Übereinstimmung zwischen den experimentellen Daten und den berechneten Ergebnissen sind ziemlich gut.

References

1 Bsebsu, F. M.; Bede, G.: Thermal hydraulic analysis and design of the WWR-M2 nuclear research reactor power upgrading. Kerntechnik, 67 (2002) 10310.1515/kern-2002-0044Search in Google Scholar

2 Lim, I.; Sim, K.; Heo, Y.; Rhee, B.; Hwang, W.; Oh, S.; Suk, H.: Development of a 2D conduction code for a finned fuel element analysis. Nucl. Eng. and Design, 122 (1990) 15710.1016/0029-5493(90)90204-BSearch in Google Scholar

3 Mele, I.; Zefran, B.: A Computer Program for Calculating Natural Convection Flow Parameters in TRIGA Core. TRISTAN. IJS-DP-6548 J. Stefan Institute, Ljubljana, Slovenia, 1992Search in Google Scholar

4 Haag, J. A.; Levine, S. H.: Thermal analysis of the Pennsylvania State University Breazeale nuclear reactor. Nucl. Technol. 19 (1973) 610.13182/NT73-A31313Search in Google Scholar

5 El-Messiry, A. M.: Reactivity accident analysis during natural core cooling operation of ETRR-2. Annals of Nuclear Energy 27 (2000) 142710.1016/S0306-4549(99)00126-7Search in Google Scholar

6 Feltus,M. A.; Miller,W. S.: Three-dimensional coupled kinetics/thermal-hydraulic benchmark TRIGA experiments. Annals of Nuclear Energy 27 (2000) 77110.1016/S0306-4549(99)00087-0Search in Google Scholar

7 Mele, I.; Ravnik, M.; Trkov, A.: Triga Mark-II benchmark experiment, part I: steady state operation. Nucl. Technol. 105 (1994) 3710.13182/NT94-A34909Search in Google Scholar

8 Safety Analysis Report for the ITU TRIGA Mark-II Reactor. August 1978Search in Google Scholar

9 Yavuz, H.; Bayülken, A.; Can, B.; Kurul,N.; Baytaþ, C.; Büke, T.; Aydy´n, M.; S¸ is¸man, A.: Computerization of ITU TRIGA Mark-II console. Twelfth Eurepean TRIGA Users Conference, Pitesti, Romania, Sep 28-Oct 1, 1992, p. 3–1Search in Google Scholar

10 Lewis, E. E.: A transient heat conduction model for reactor fuel elements. Nucl. Eng. and Design, 15 (1971) 3310.1016/0029-5493(71)90053-7Search in Google Scholar

11 Lewis, E. E.: Nuclear Power Reactor Safety. John Wiley & Sons, 1977Search in Google Scholar

12 Persic, A.; Ravnik, M.; Slavic, S.; Zagar, T.: TRIGLAV- A Program Package for Research Reactor Calculations. March 1999 IAEA 1370/1Search in Google Scholar

13 Can, B.; Yavuz, H.; Akbay, E.: The investigation of nonlinear dynamics behavior of ITU TRIGA Mark-II reactor. Eleventh European TRIGA Users Conference, Heidelberg, September 11–13, 1990, p. 2.39Search in Google Scholar

14 Holman, J. P.: Heat Transfer. McGraw-Hill Book Company, 1989Search in Google Scholar

15 Büke, T.; Yavuz, H.: Calculation of the reactivity worth for TRIGA core fuel elements by means of the two-dimensional, two-group pertubation theory. Kerntechnik, 63 (1998) 27310.1515/kern-1998-635-614Search in Google Scholar

Received: 2003-01-22

Published Online: 2022-03-16

You are currently not able to access this content.

Articles in the same Issue

https://doi.org/10.1515/kern-2003-0087