CANDU REAKTÖRLERİNDE ThC VE LWR YAKIT ATIĞI KARIŞIMI KULLANIMININ İNCELENMESİ

Bu çalışmada; ThC ve Hafif su reaktörü (LWR) yakıt atığı karışımının CANDU reaktörlerinde kullanılabilirliği ve reaktör performansına etkisi araştırılmıştır. Bunun için yakıt olarak % 100 UO2, % 100 LWR yakıt atığı ve % 40 ThC + % 60 LWR yakıt atığı karışımı kullanılmıştır. Hesaplamalar tek boyutlu SCALE 4.4a bilgisayar sistem kodu yardımıyla yapılmıştır. Yapılan hesaplamalar sonucunda, k¥ = 1.06 sınır değerinde bu yakıtlar için yanma dereceleri sırasıyla 7.700, 27.000 ve 11.000 MW.D/MT bulunmuş ve reaktör işletim süreleri 170, 660, 280 gün elde edilmiştir. Buna bağlı olarak, ThC ile LWR yakıt atığı karışımının doğal UO2 yakıtına nazaran kritiklik ve yanma derecesi açısından çok iyi nükleer performans sergilediği görülmüştür.

Anahtar Kelimeler:

CANDU Reaktörü, Toryum, LWR yakıt atığı.

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Choi, H. B., Rhee, B. W., Park, H. S., “Physics Study on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU (DUPIC)”, Nuclear Science and Engineering, Cilt 126, 80, 1997.
Choi, H., Ko, W. I., Yang, M. S., “Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors-I: DUPIC Fuel Fabrication Cost”, Nuclear Technology, Cilt 134, 110-129, 2001.
Choi, H., Ko, W. I., Yang, M. S., Namgung, I., Na, B.G., “Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors-II: DUPIC Fuel-Handling Cost”, Nuclear Technology, Cilt 134, 130-148, 2001.
Kim, D.H., Choi, H., Yang W.S., Kim, J.K., “Composition Heterogenetiy Analysis for Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors (DUPIC)-I: Deterministic Analysis” Nuclear Science and Engineering, Cilt 137, 23-27, 2001.
Şahin, S., Şahin, H.M., Alkan, M., Yıldız, K., “An Assessment of Thorium and Spent LWR-Fuel Utilization Potential in CANDU Reactors”, Energy Conversion and Management, Cilt 45, 1067-1085, 2004.
Alkan, M., Reutilization of Nuclear Fuel Wastes, PhD Thesis in Turkish, Gazi University, Institute of Science and Technology, Ankara, Turkey, 2003.
Şahin, S., Yapıcı, H., “Rejuvenation of LWR Spent Fuel in Fusion Blankets” Annals of Nuclear Energy, Cilt 25, No 16, 1317-1339, 1998.
Şahin, S., Übeyli, M., “LWR spent fuel transmutation in a high power density fusion reactor” Annals of Nuclear Energy, Cilt 31, No 8, 871-890, 2004.
Übeyli, M., “Transmutation of Minor Actinides Discharged from LMFBR Spent Fuel in a High Power Density Fusion Reactor”, Energy Conversion and Management, Cilt 45, 3219-3238, 2004.
Boczar, P. G., Chan, P. S. W., Dyck, G. R., Ellis, R. J., Jones, R. T., Sullivan, J. D., Taylor, P., “Thorium Fuel-Cycle Studies for CANDU Reactors, Thorium Fuel Utilization: Options and Trends”, Proceedings of three IEAE meetings held in Vienna in 1997, 1998 and 1999, IEAE-TECDOC-1319, 25-41, 2002.
Boczar, P. G., Dyck, G. R., Chan, P. S. W., Buss, D. B., “Recent Advances in Thorium Fuel Cycles for CANDU Reactors, Thorium Fuel Utilization: Options and Trends”, Proceedings of three IEAE meetings held in Vienna in 1997, 1998 and 1999, IEAE-TECDOC-1319, 104-120, 2002.
Critoph, E., “Prospects for Self–sufficient Equilibrium Thorium Cycles in CANDU Reactors”, Atomic Energy of Canada Ltd., Report AECL-5501, 1976.
Galperin, A., Todosow, M., “Assessment of Homogeneous Thorium/Uranium Fuel for Pressurized Water Reactors”, Nuclear Technology, Cilt 138, 111-121, 2002.
Hatcher, S. R., “Thorium Cycle in Heavy Water Moderated Pressure Tube (CANDU) Reactors”, Atomic Energy of Canada Ltd., Report AECL-5398, 1976.
IAEA. “Status and Prospects of Thermal Breeders and their Effect on Fuel Utilization”, Technical Report Series No. 195, International Atomic Energy Agency, Vienna, 1979.
Loewen, E. P., Wilson, R. D., Hohorst, J.K., Kumar, A.S., “Preliminary Frapcon-3th Steady-State Fuel Analysis of ThO2 and UO2 Fuel Mixtures”, Nuclear Technology, Cilt 136, 261-277, 2001.
Şahin, S., Yıldız K., Acır A., “Power Flattening In The Fuel Bundle of a CANDU Reactor”, Nuclear Engineering and Design, Cilt 232, 7-18, 2004.
“International Methods Handbook”, 10th Edition, American Society for Metals, Cilt 3, 1990.
Ma, B. M. “Nuclear Reactor Materials and Applications”, Van Nostrand Reinhold Company Limited, Molly Millars Lane, Wokingham, Berkshire, England, 1983.
Lamarsh, J. R., Baratta, A. J., “Introduction to Nuclear Engineering”, Third Edition, Prentice Hall, Upper Saddle River, New Jersey 07458, 2001.
Manson, B., Pigford, T. H., Levi, H. W., “Nuclear Chemical Engineering”, New York: McGraw-Hill, 1981.
Şahin, S., Şahin, H.M., Yıldız, K., “Investigation of The Effects of The Resonance Absorption in a Fusion Breeder Blanket”, Annals of Nuclear Energy, Cilt 29, 1641, 2002.
Yıldız, K., “An Investigation of the neutron energy group structures and resonance effects in a Fusion-Fission Hybrid Reactors Fuelling with ThO2”, Annals of Nuclear Energy, Cilt 32, 101-118, 2004.
Jordan W. C., Bowman, S. M., “Scale Cross-Section Libraries”, NUREG/CR-0200, Revision 6, 3, section M4, ORNL/NUREG/CSD-2/V3/R6, Oak Ridge National Laboratory, 2000.
Petrie L. M., “SCALE System Driver”, NUREG/CR-0200, Revision 6, 3, Section M1, ORNL/NUREG/CSD-2/R6, Oak Ridge National Laboratory, 2000.
Greene N. M., Petrie, L. M., Westfall, R. M., “NITAWL-II, Scale System Module For Performing Resonance Shielding and Working Library Production”, NUREG/CR-0200, Revision 6, 2, Section F2, ORNL/NUREG/CSD-2/V2/R6, Oak Ridge National Laboratory, 2000.
Greene N. M., “BONAMI, Resonance Self-Shielding by the Bondarenko Method”, NUREG/CR-0200, Revision 6, 2, section F1, ORNL/NUREG/CSD-2/V2/R6, Oak Ridge National Laboratory, 2000. Bondarenko I. I. (Ed.), “Group Constants For Nuclear Reactor Calculations”, Consultants Bureau, New York, 1964.
Landers N. F., Petrie, L. M., “CSAS, Control Module for Enhanced Criticality Safety Analysis Sequences”, NUREG/CR-0200, Revision 6, 1, Section C4, ORNL/NUREG/CSD-2/V1/R6, Oak Ridge National Laboratory, 2000.
Greene N. M., Petrie, L. M., “XSDRNPM, A One-Dimensional Discrete-Ordinates Code For Transport Analysis”, NUREG/CR-0200, Revision 6, 2, Section F3, ORNL/NUREG/CSD-2/V2/R6, Oak Ridge National Laboratory, 2000.
Şahin S., H. Yapıcı, S. Ünalan, “ERDEMLI, A Computer Program to Process ANISN Output Data”, Gazi University, Ankara, Turkey, 1991.
Graves, H. W. Jr., “Nuclear Fuel Management”, John Wiley & Sons, New York, 1979.
Seelmann-Eggebert, W., Pfennig, G., Münzel, H., Klewe-Nebenius, H., “Chart of the Nuclides”, 5th edition, Kernforschungszentrum Karlsruhe Gmbh, Germany, 1981.