Sipping tests for the irradiated fuel elements of the TR-2 research reactor

References

1 Operation and Maintenance of Spent Fuel Storage and Transportation Casks/Containers. International Atomic Energy Agency, IAEA-TECDOC-1532, 2007Search in Google Scholar

2 Regulations for the Safe Transport of Radioactive Material, Safety Requirements. International Atomic Energy Agency, No: TS-R-1, 2005Search in Google Scholar

3 Terremoto, L. A.A.; Seerban, R. S.; Zeituni, C. A.; da Silva, J. E. R.; Silva, A. T.; Castanheira, M.; Lucki, de A., DamyG. M., Teodoro, C. A.: A model for release of fission products from a breached fuel plate under wet storage. Progress in Nuclear Energy50 (2008) 818Search in Google Scholar

4 Safety Analysis Report of TR-2 Reactor, Turkish Atomic Energy Authority2006Search in Google Scholar

5 Centre d'Etudes Nucléaire de Grenoble, Project du Réactuer TR-2 5 MW de Çekmece. Report CEN-G PI-SEREG/1012, 1974Search in Google Scholar

6 Bastürk, M.; Tatlisu, H.; Böck, H.: Nondestructive inspection of fresh WWER-440 fuel assemblies. Journal of Nuclear Materials350 (2006) 240Search in Google Scholar

7 Chae, H. T.; Kim, H.; Lee, C. S.; Jun, B. J.; Park, J. M.; Kim, C. K.; Sohn, D. S.: Irradiation tests for U₃Si–Al dispersion fuels with aluminum cladding. Journal of Nuclear Materials373 (2008) 9 10.1016/j.jnucmat.2007.03.270Search in Google Scholar

8 Perrotta, J. A.; Terremoto, L. A. A.; Zeituni, C. A.: Experience on wet storage spent fuel sipping at IEAR1 Brazilian Research Reactor. Annals of Nuclear Energy25 (1998) 237 10.1016/S0306-4549(97)00039-XSearch in Google Scholar

9 Zeituni, C. A.; Terremoto, L. A. A.; da Silva, J. E. R.: Failed MTR fuel element detect in a Sipping tests. American Nuclear Energy Symposium, OSTI ID: 841352, Miami, USA, October, 2004Search in Google Scholar

10 Ooms, L.; Massaut, V.; Noynaert, L.; Braeckeveldt, M.; Geenen, G.: Dry Storage of the BR3 spent fuel in the Castor BR3 cask. Transactions of Seventh International Topical Meeting on Research Reactor Fuel Management, Aix-en-Provence, France, March2003, p. 17110.1115/ICEM2003-5015Search in Google Scholar

11 Auziere, P.; Gubel, P.: The leaking RTR aluminide spent fuel management LA Hague reprocessing plant flexibility. Transactions of Seventh International Topical Meeting on Research Reactor Fuel Management, Aix-en-Provence, France, March2003, p. 203Search in Google Scholar

12 Smith, M. L.; Bignell, L. J.; Alexiev, D.; Mo, L.: Sipping test: Checking for failure of fuel elements at the OPAL REACTOR. Nuclear Engineering and Technology42 (2010) 125Search in Google Scholar

13 Terremoto, L. A. A.; Zeituni, C. A.; Perrotta, J. A.; da Silva, J. E. R.: Gamma-ray spectroscopy on irradiated MTR fuel elements. Nuclear Instruments and Methods in Physics Research A450 (2000) 49510.1016/S0168-9002(00)00250-3Search in Google Scholar

14 Lewis, B. J.; MacDonald, R. D.; Bonin, H. W.: Release of iodine and noble gas fission products from defected fuel elements during reactor shutdown and start-up. Nuclear Technology92 (1990) 315Search in Google Scholar

15 Chun, M. H.; Tak, N.; Lee, S.: Development of a computer code to estimate the fuel rod failure using primary coolant activities of operating PWRS. Annals of. Nuclear Energy25 (1998) 753Search in Google Scholar

16 Kim, J. Y.; Kim, C. L.; Chung, C. H.: Modelling of nuclide releases from perforated radioactive paraffin waste containers. Journal of Nuclear Materials303 (2002) 92Search in Google Scholar

17 Elements Conbustibles Réactuer TR-1, Spécifications Techniques Compagnie pour l'Etude et la Réalisation de Combustibles Atomiques, CERCA, 1973Search in Google Scholar

18 Iqbal, M.; Mirza, N. M.; Mirza, S. M.; Ayazuddin, S. K.: Study of the void coefficients of reactivity in a typical pool type research reactor. Annals of Nuclear Energy24 (1997) 177Search in Google Scholar

19 Sevdik, B.; Yavuz, H.: Experimental measurement for plate temperatures of MTR fuel elements fuel elements cooled in stagnant air and comparison with computed results. Kerntechnik63 (1998) 267–272Search in Google Scholar

20 Yılmazer, A.; Yavuz, H.: Analysis of a total loss of pool water accident in MTR-type research reactors. Kerntechnik69 (2004) 154Search in Google Scholar

21 Standard Electrode Coaxial Ge Detectors. CANBERRA, Canberra Industries Inc, 2009Search in Google Scholar

22 Knoll, G. F.: Radiation Detection and Measurement. John Wiley & Sons Inc., New York, 1989Search in Google Scholar

23 GammaVision-32 Gamma Ray Spectrum Analysis and MCA Emulator, ORTEC, USA, 2009Search in Google Scholar