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CANDU REAKTÖRLERİNDE ThO2 ve 233UO2 YAKIT KARIŞIMI KULLANIMININ İNCELENMESİ

Yıl 2007, Cilt: 22 Sayı: 3, 0 - , 15.02.2013

Öz

Bu çalışmada; (Th+233U)O2 yakıt karışımının CANDU reaktörlerinde kullanılabilirliği ve reaktör başarımınaetkisi araştırılmıştır. Bunun için yakıt olarak %98 ThO2 + %2 233UO2 yakıt karışımı kullanılmıştır. Nötronikveriler, tek boyutlu SCALE 4.4a nükleer hesaplama kodu yardımıyla elde edilmiştir. Reaktör kritiklik ve yanmaderecesi değerleri tam güçte 20 yıl için hesaplanmıştır. Yapılan hesaplamalar sonucunda, reaktör kritikliğinink∞=~1,3 le başladığı ve 2. yıl sonundan itibaren 20 yıl boyunca k∞=1,06 sınır değerinin üzerinde olduğugörülmüştür. Yanma derecesi 2. yıl sonunda 45.216 MW.D/MT ve 20. yılın sonunda 558.061 MW.D/MT gibiçok yüksek bir değer elde edilmiştir. Bu çalışma, toryumun çok düşük oranda (%2) fisil izotop karışımlarıylaCANDU reaktörlerinde yakıt olarak kullanılabileceğini göstermektedir.

Kaynakça

  • 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
  • , 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,
  • -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
  • , 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-
  • , 2004.
  • Ünalan, S., Ayata, T., Akansu, S. O., Erişen, A.,
  • Bölükbaşı, A., “Light and heavy water cooled
  • hybrid reactors for rejuvenation of LWR spent
  • fuels”, Energy Conversion & Management, Cilt
  • , 2567-2587, 2003.
  • Şahin, S., Yapıcı, H., “Rejuvenation Of Light
  • Water Reactor Spent Fuel In Fusion Blankets”,
  • Annals of Nuclear Energy, Cilt 25, 1317-1339,
  • -
  • Ünalan, S., “Rejuvenation of the LWR spent fuel
  • in (D–T) driven hybrid reactors”, Fusion
  • Engineering and Design, Cilt 38, 393-416, 1998.
  • Şahin, S., Yapıcı, H., “Neutronic analysis of a
  • thorium fusion breederwith enhanced protection
  • against nuclear weapon proliferation”, Annals of
  • Nuclear Energy, Cilt 26, 13-27, 1999.
  • Yapıcı, H., Şahin, N., Bayrak, M., “Investigation
  • of neutronic potential of a moderated (D-T)
  • fusion driven hybrid reactor fueled with thorium
  • to breed fissile fuel for LWRs”, Energy
  • Conversion & Management, Cilt 41, 435-447,
  • -
  • Şahin, S., Özceyhan, V., Yapıcı, H., “Proliferation
  • hardening and power flattening of a thorium
  • fusion breeder with triple mixed oxide fuel.”,
  • Annals of Nuclear Energy, Cilt 28, 203, 2001.
  • Yapıcı H., Übeyli M., Yalçın Ş., “Neutronic
  • analysis of PROMETHEUS reactor fueled with
  • various compounds of thorium and uranium”,
  • Annals of Nuclear Energy, Cilt 29, 1871-1889,
  • -
  • İpek O., “Analysis of the neutronic data in infinite
  • medium using fusion neutron source for various
  • material compositions”, Energy Conversion &
  • Management, Cilt 44, 439-458, 2003.
  • Akansu S. O., Ünalan S., “Investigation of the
  • flattened fissile fuel enrichment possibility with a
  • (D,T) driven hybrid blanket cooled by flibe
  • (Li2BeF4 )”, Annals of Nuclear Energy, Cilt 29,
  • -302, 2002.
  • İpek O., “Investigation of the in .nite medium
  • integral neutronic data for incident fusion source
  • neutrons”, Annals of Nuclear Energy, Cilt 29,
  • -1523, 2002.
  • Yapıcı H., İpek O., Übeyli M., “Investigation of
  • the performance parameters and temperature
  • distribution in fuel rod dependent on operation
  • periods and first wall loads in fusion-fission
  • reactor system fueled with ThO2”, Energy
  • Conversion & Management, Cilt 44, 573-595,
  • -
  • Yapıcı H., Bayrak M., “Neutronic analysis of
  • denaturing plutonium in a thorium fusion breeder
  • and power flattening”, Energy Conversion &
  • Management, Cilt 46, 1209-1228, 2005.
  • Yapıcı H., İpek O., “Neutronic performance of
  • coupled hybrid blanket fueled with ThO2 and
  • UO2”, Energy Conversion & Management, Cilt
  • , 1853-1873, 2003.
  • Şahin S., Yapıcı H., Şahin N., “Neutronic
  • performance of proliferation hardened thorium
  • fusion breeders”, Fusion Engineering and
  • Design, Cilt 54, 63-77, 2001.
  • Şahin, S., Şahin, H.M., Sözen A., Bayrak M.,
  • “Power flattening and minor actinide burning in a
  • thorium fusion breeder”, Energy Conversion &
  • Management, Cilt 43, 799-815, 2002.
  • Yapıcı H., “Power flattening of an inertial fusion
  • energy breeder with mixed ThO2- UO2 fuel”,
  • Fusion Engineering and Design, Cilt 65, 89-108,
  • -
  • Şahin S., Yapıcı H., Bayrak M., “Spent mixed
  • oxide fuel rejuvenation in fusion breeders”,
  • Fusion Engineering and Design, Cilt 47, 9-23,
  • -
  • 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, IEAETECDOC-
  • , 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-
  • , 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-
  • , 2001.
  • Şahin, S., Yıldız, K., Şahin, H. M., Şahin N., Acır,
  • A., “Increased fuel burn up in a CANDU thorium
  • reactor using weapon grade plutonium”, Nuclear
  • Engineering and Design, Cilt 236, 1778-1788,
  • -
  • Şahin, S., Yıldız, K., Şahin, H. M., Acır, A.,
  • “Investigation of CANDU reactors as a thorium
  • burner”, Energy Conversion & Management,
  • Cilt 47, 1661-1675, 2006.
  • J. Stephen Herring , Philip E. MacDonald, Kevan
  • D. Weaver, Craig Kullberg “Low cost,
  • proliferation resistant, uranium–thorium dioxide
  • fuels for light water reactors”, Nuclear
  • Engineering and Design, Cilt 203, 65-85, 2001.
  • Yapıcı H., “Temperature distribution in mixed
  • ThO2-UO2 fuel rods located in blanket of an
  • inertial fusion energy breeder”, Annals of
  • Nuclear Energy, Cilt 29, 2187-2209, 2002.
  • L. Mathieu, D. Heuer, R. Brissot, C. Garzenne, C.
  • Le Brun, D. Lecarpentier, E. Liatard, J.-M.
  • Loiseaux, O.Meplan, E. Merle-Lucotte, A. Nuttin,
  • E. Walle, J. Wilson, “The thorium molten salt
  • reactor: Moving on from the MSBR”, Progress in
  • Nuclear Energy, Cilt 48, 664-679, 2006.
  • Acır, A., “CANDU Reaktörlerinde ThC ve LWR
  • Yakıt Atığı Karışımı Kullanımının İncelenmesi”,
  • Gazi Üniversitesi Mühendislik-Mimarlık
  • Fakültesi Dergisi, Cilt 20, 43-51, 2005.
  • 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.
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  • 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
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Yıl 2007, Cilt: 22 Sayı: 3, 0 - , 15.02.2013

Öz

Kaynakça

  • 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
  • , 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,
  • -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
  • , 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-
  • , 2004.
  • Ünalan, S., Ayata, T., Akansu, S. O., Erişen, A.,
  • Bölükbaşı, A., “Light and heavy water cooled
  • hybrid reactors for rejuvenation of LWR spent
  • fuels”, Energy Conversion & Management, Cilt
  • , 2567-2587, 2003.
  • Şahin, S., Yapıcı, H., “Rejuvenation Of Light
  • Water Reactor Spent Fuel In Fusion Blankets”,
  • Annals of Nuclear Energy, Cilt 25, 1317-1339,
  • -
  • Ünalan, S., “Rejuvenation of the LWR spent fuel
  • in (D–T) driven hybrid reactors”, Fusion
  • Engineering and Design, Cilt 38, 393-416, 1998.
  • Şahin, S., Yapıcı, H., “Neutronic analysis of a
  • thorium fusion breederwith enhanced protection
  • against nuclear weapon proliferation”, Annals of
  • Nuclear Energy, Cilt 26, 13-27, 1999.
  • Yapıcı, H., Şahin, N., Bayrak, M., “Investigation
  • of neutronic potential of a moderated (D-T)
  • fusion driven hybrid reactor fueled with thorium
  • to breed fissile fuel for LWRs”, Energy
  • Conversion & Management, Cilt 41, 435-447,
  • -
  • Şahin, S., Özceyhan, V., Yapıcı, H., “Proliferation
  • hardening and power flattening of a thorium
  • fusion breeder with triple mixed oxide fuel.”,
  • Annals of Nuclear Energy, Cilt 28, 203, 2001.
  • Yapıcı H., Übeyli M., Yalçın Ş., “Neutronic
  • analysis of PROMETHEUS reactor fueled with
  • various compounds of thorium and uranium”,
  • Annals of Nuclear Energy, Cilt 29, 1871-1889,
  • -
  • İpek O., “Analysis of the neutronic data in infinite
  • medium using fusion neutron source for various
  • material compositions”, Energy Conversion &
  • Management, Cilt 44, 439-458, 2003.
  • Akansu S. O., Ünalan S., “Investigation of the
  • flattened fissile fuel enrichment possibility with a
  • (D,T) driven hybrid blanket cooled by flibe
  • (Li2BeF4 )”, Annals of Nuclear Energy, Cilt 29,
  • -302, 2002.
  • İpek O., “Investigation of the in .nite medium
  • integral neutronic data for incident fusion source
  • neutrons”, Annals of Nuclear Energy, Cilt 29,
  • -1523, 2002.
  • Yapıcı H., İpek O., Übeyli M., “Investigation of
  • the performance parameters and temperature
  • distribution in fuel rod dependent on operation
  • periods and first wall loads in fusion-fission
  • reactor system fueled with ThO2”, Energy
  • Conversion & Management, Cilt 44, 573-595,
  • -
  • Yapıcı H., Bayrak M., “Neutronic analysis of
  • denaturing plutonium in a thorium fusion breeder
  • and power flattening”, Energy Conversion &
  • Management, Cilt 46, 1209-1228, 2005.
  • Yapıcı H., İpek O., “Neutronic performance of
  • coupled hybrid blanket fueled with ThO2 and
  • UO2”, Energy Conversion & Management, Cilt
  • , 1853-1873, 2003.
  • Şahin S., Yapıcı H., Şahin N., “Neutronic
  • performance of proliferation hardened thorium
  • fusion breeders”, Fusion Engineering and
  • Design, Cilt 54, 63-77, 2001.
  • Şahin, S., Şahin, H.M., Sözen A., Bayrak M.,
  • “Power flattening and minor actinide burning in a
  • thorium fusion breeder”, Energy Conversion &
  • Management, Cilt 43, 799-815, 2002.
  • Yapıcı H., “Power flattening of an inertial fusion
  • energy breeder with mixed ThO2- UO2 fuel”,
  • Fusion Engineering and Design, Cilt 65, 89-108,
  • -
  • Şahin S., Yapıcı H., Bayrak M., “Spent mixed
  • oxide fuel rejuvenation in fusion breeders”,
  • Fusion Engineering and Design, Cilt 47, 9-23,
  • -
  • 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, IEAETECDOC-
  • , 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-
  • , 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-
  • , 2001.
  • Şahin, S., Yıldız, K., Şahin, H. M., Şahin N., Acır,
  • A., “Increased fuel burn up in a CANDU thorium
  • reactor using weapon grade plutonium”, Nuclear
  • Engineering and Design, Cilt 236, 1778-1788,
  • -
  • Şahin, S., Yıldız, K., Şahin, H. M., Acır, A.,
  • “Investigation of CANDU reactors as a thorium
  • burner”, Energy Conversion & Management,
  • Cilt 47, 1661-1675, 2006.
  • J. Stephen Herring , Philip E. MacDonald, Kevan
  • D. Weaver, Craig Kullberg “Low cost,
  • proliferation resistant, uranium–thorium dioxide
  • fuels for light water reactors”, Nuclear
  • Engineering and Design, Cilt 203, 65-85, 2001.
  • Yapıcı H., “Temperature distribution in mixed
  • ThO2-UO2 fuel rods located in blanket of an
  • inertial fusion energy breeder”, Annals of
  • Nuclear Energy, Cilt 29, 2187-2209, 2002.
  • L. Mathieu, D. Heuer, R. Brissot, C. Garzenne, C.
  • Le Brun, D. Lecarpentier, E. Liatard, J.-M.
  • Loiseaux, O.Meplan, E. Merle-Lucotte, A. Nuttin,
  • E. Walle, J. Wilson, “The thorium molten salt
  • reactor: Moving on from the MSBR”, Progress in
  • Nuclear Energy, Cilt 48, 664-679, 2006.
  • Acır, A., “CANDU Reaktörlerinde ThC ve LWR
  • Yakıt Atığı Karışımı Kullanımının İncelenmesi”,
  • Gazi Üniversitesi Mühendislik-Mimarlık
  • Fakültesi Dergisi, Cilt 20, 43-51, 2005.
  • 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 Metals 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,
  • -
  • 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-
  • , 2004.
  • Jordan W. C., Bowman, S. M., “Scale Cross-
  • Section Libraries”, NUREG/CR-0200, Revision
  • , 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-
  • /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,
  • -
  • 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-
  • /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-
  • /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”,
  • th edition, Kernforschungszentrum Karlsruhe
  • Gmbh, Germany, 1981.
  • Leggertt, R. D., Omberg, R. P., “Mixed oxide fuel
  • development”, Proceedings of the International
  • Conference on Fast Breeder Systems:
  • Experience Gained and Path to Economical
  • Power Generation, American Nuclear Society,
  • Richland, W.A, 13-17, September 1987.
  • Waltar, A. E., Deitrich, L. W., “Status of research
  • on key LMR safety issues“, Nucl. Saf., Cilt:29
  • (2), 125, 1988.
Toplam 249 adet kaynakça vardır.

Ayrıntılar

Birincil Dil Türkçe
Bölüm Makaleler
Yazarlar

Necmettin Şahin Bu kişi benim

Yayımlanma Tarihi 15 Şubat 2013
Gönderilme Tarihi 15 Şubat 2013
Yayımlandığı Sayı Yıl 2007 Cilt: 22 Sayı: 3

Kaynak Göster

APA Şahin, N. (2013). CANDU REAKTÖRLERİNDE ThO2 ve 233UO2 YAKIT KARIŞIMI KULLANIMININ İNCELENMESİ. Gazi Üniversitesi Mühendislik Mimarlık Fakültesi Dergisi, 22(3).
AMA Şahin N. CANDU REAKTÖRLERİNDE ThO2 ve 233UO2 YAKIT KARIŞIMI KULLANIMININ İNCELENMESİ. GUMMFD. Mart 2013;22(3).
Chicago Şahin, Necmettin. “CANDU REAKTÖRLERİNDE ThO2 Ve 233UO2 YAKIT KARIŞIMI KULLANIMININ İNCELENMESİ”. Gazi Üniversitesi Mühendislik Mimarlık Fakültesi Dergisi 22, sy. 3 (Mart 2013).
EndNote Şahin N (01 Mart 2013) CANDU REAKTÖRLERİNDE ThO2 ve 233UO2 YAKIT KARIŞIMI KULLANIMININ İNCELENMESİ. Gazi Üniversitesi Mühendislik Mimarlık Fakültesi Dergisi 22 3
IEEE N. Şahin, “CANDU REAKTÖRLERİNDE ThO2 ve 233UO2 YAKIT KARIŞIMI KULLANIMININ İNCELENMESİ”, GUMMFD, c. 22, sy. 3, 2013.
ISNAD Şahin, Necmettin. “CANDU REAKTÖRLERİNDE ThO2 Ve 233UO2 YAKIT KARIŞIMI KULLANIMININ İNCELENMESİ”. Gazi Üniversitesi Mühendislik Mimarlık Fakültesi Dergisi 22/3 (Mart 2013).
JAMA Şahin N. CANDU REAKTÖRLERİNDE ThO2 ve 233UO2 YAKIT KARIŞIMI KULLANIMININ İNCELENMESİ. GUMMFD. 2013;22.
MLA Şahin, Necmettin. “CANDU REAKTÖRLERİNDE ThO2 Ve 233UO2 YAKIT KARIŞIMI KULLANIMININ İNCELENMESİ”. Gazi Üniversitesi Mühendislik Mimarlık Fakültesi Dergisi, c. 22, sy. 3, 2013.
Vancouver Şahin N. CANDU REAKTÖRLERİNDE ThO2 ve 233UO2 YAKIT KARIŞIMI KULLANIMININ İNCELENMESİ. GUMMFD. 2013;22(3).