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Investigation of Some Neutronic Values for Np and Am Fuel Rods in a Boiling Water Reactor Modeling

Yıl 2020, Cilt: 15 Sayı: 1, 140 - 147, 31.05.2020
https://doi.org/10.29233/sdufeffd.705690

Öz

In this study, some neutronic values were investigated in modeling three-dimensional boiling water reactor (BWR) using Monte Carlo method. In BWR modeling, the reactor core was designed by dividing it into 8x8 type square lattices and each square lattice in itself into 7x7 type small square lattices. In this study, small square lattices of 7x7 type were created by using Neptunium (Np) and Americium (Am) minor actinides at the rate of 0.02-0.1% as fuel rod, Zirkolay-2 (Zr-2) as fuel clad, water as coolant. B4C control rods were placed in 8x8 type square lattices in the cruciform area. In BWR modeling, keff, fission energy and heat deposition rate neutronic values were calculated for Np and Am fuel rods at the rate of 0.02-0.1% and Zr-2 fuel clad. Three-dimensional modeling of the BWR system was designed using MCNPX-2.7.0 Monte Carlo method and ENDF/B-VIII.0 nuclear data library.

Kaynakça

  • [1] J. Zakova, J. Wallenius, "Multirecycling of Pu, Am and Cm in BWR," Ann. Nucl. Energy, 58, 255-267, 2013.
  • [2] J. Loberg, M. Österlung, J. Blomgren, K. Bejmer, "Neutron detection-based void monitoring in boiling water reactors," Nucl. Sci. Eng., 164, 69-79, 2010.
  • [3] J. Loberg, Novel Diagnostics and Computational Methods of Neutron Fluxes in Boiling Water Reactors, Digital Comprehensive Summaries of Uppsala Dissertations from The Faculty of Science and Technology 715, ISSN: 1651-6214, 2010.
  • [4] R. Fridstrom, "Response of The Gamma TIP Detectors in a Nuclear Boiling Water Reactor," UPTEC F10 042, ISSN: 1401-5757, 2010.
  • [5] K. Edsinger, K. L. Murty, "LWR pellet-cladding interactions: materials solutions to SCC," JOM, 53, 9-13, 2001.
  • [6] C. D. Williams, M. Marlowe, R. B. Adamson, S. B. Wisner, R. A. Rand, J. S. Armijo, "Zircaloy-2 lined zirkonium barrier fuel cladding," Twelfth International Symposium, ASTM STP 1295, 1996, pp. 676–694.
  • [7] C. Wan, X. Zou, L. Cao, H. Wu, "Covariance comparisons between ENDF/B-VII.I and ENDF/B-VIII.0 with application for the UAM-LWR exercises," Ann. Nucl. Energy, 138, 107-183, 2020.
  • [8] H. O. Wooten, "An application for streamlined and automated ENDF Cross Section Analysis and visualization (EXSAN)," Ann. Nucl. Energy, 129, 482-486, 2019.
  • [9] O. Kabach, A. Chetaine, A. Benchrif, "Processing of JEFF-3.3 and ENDF/B-VIII.0 and testing with critical benchmark experiments and TRIGA Mark II research reactor using MCNPX," Appl. Radiat. Isot., 150, 146-156, 2019.
  • [10] B. Şarer, A. Aydın, M. Günay, M. E. Korkmaz, E. Tel, "Calculations of neutron induced production cross-sections of 180,182,183,184,186W up to 20 MeV," Ann. Nucl. Energy, 36, 417-426, 2009.
  • [11] M. Günay, "Investigation of radiation damage in structural material of APEX reactor by using Monte Carlo Method," Ann. Nucl. Energy, 53, 59-63, 2013.
  • [12] H. W. Bertini, "Low-energy intranuclear cascade calculation," Phys. Rev., 131, 1801, 1963.
  • [13] H. W. Bertini, "Intranuclear-Cascade calculation of the secondary nucleon spectra from nucleon–nucleus interactions in the energy range 340 to 2900 MeV and comparisons with experiment," Phys. Rev., 188, 1711, 1969.
  • [14] Y. Yariv, Z. Fraenkel, "Intranuclear Cascade Calculation of High-Energy Heavy-Ion Interactions," Phys. Rev. C, 20, 2227, 1979.
  • [15] Y. Yariv, Z. Fraenkel, "Intranuclear Cascade Calculation of High Energy Heavy Ion Collisions: Effect of Interactions Between Cascade Particles," Phys. Rev. C, 24, 488, 1981.
  • [16] A. Boudard, J. Cugnon, S. Leray, C. Volant, "Intranuclear Cascade Model for a Comprehensive Description of Spallation Reaction Data," Phys. Rev. C, 66, 615, 2002.
  • [17] J. Cugnon, "Proton-Nucleus Interaction at High Energy," Nucl. Phys. A, 462, 751-780, 1987.
  • [18] J. Cugnon, C. Volant, S. Vuillier, "Improved Intranuclear Cascade Model for Nucleon-Nucleus Interactions," Nucl. Phys. A, 620, 475-509, 1997.
  • [19] S. G. Mashnik, V. D. Toneev, "MODEX – The Program for Calculation of The Energy Spectra of Particles Emitted in The Reactions of Pre-equilibrium and Equilibrium Statistical Decays," JINR P4-8417, 25, 1974.
  • [20] L. Dresner, "EVAP—a FORTRAN Program for Calculating The Evaporation of Various Particles from Excited Compound Nuclei," Report ORNL/TM-196, 1962.
  • [21] A. R. Junghans, M. Jong, H. G. Clerc, A. V. Ignatyuk, G. A. Kudyaev, K. H. Schmidt, "Projectile-Fragment Yields as a Probe for The Collective Enhancement in The Nuclear Level Density," Nucl. Phys. A, 629, 635-655, 1998.
  • [22] B. Şarer, S. Şahin, M. Günay, Y. Çelik, "Comparisons of The Calculations Using Different Codes Implemented in MCNPX Monte Carlo Transport Code for Accelerator Driven System Target," Fusion Sci. Technol., 61, 302-307, 2012.
  • [23] M. Günay, H. Kasap, "Neutronic investigation of the application of certain plutonium-mixed fluids in a fusion–fission hybrid reactor", Ann. Nucl. Energy, 63, 432–436, 2014.
  • [24] S. E. Ouahdani, H. Boukhal, L. Erradi, E. Chakir, M. Azahra, T. E. Bardouni, M. Makhloul, A. Ahmed, "A temperature effect analysis of the KRITZ-1 benchmark based on keff decomposition and using the JENDL-4.0 and ENDF/B-VII.1 libraries," Prog. Nucl. Energ., 109, 121-129, 2018.
  • [25] J. J. Duderstadt, L. J. Hamilton, Nuclear Reactor Analysis, John Wiley&Sons, Inc. 1976.
  • [26] Y. Liu, B. Kochunas, W. Martin, T. Downar, "Delayed fission energy effect on LWR normal operation and transients," Ann. Nucl. Energy, 128, 84–93, 2019.
  • [27] S. Şahin, B. Şarer, Y.Çelik, "Utilization of nuclear waste plutonium and thorium mixed fuel in candu reactors," Int. J. Energ. Res., 40, 1901–1907, 2016.
  • [28] B. Şarer, S. Şahin, Y. Çelik, M. Günay, "Evaluation of integral quantities in an accelerator driven system using different nuclear models implemented in the MCNPX Monte Carlo transport code," Ann. Nucl. Energy, 62, 382-389, 2013.

Bir Kaynar Su Reaktör Modellemesinde Np ve Am Yakıt Çubukları için Bazı Nötronik Değerlerin İncelenmesi

Yıl 2020, Cilt: 15 Sayı: 1, 140 - 147, 31.05.2020
https://doi.org/10.29233/sdufeffd.705690

Öz

Bu çalışmada Monte Carlo metodu kullanılarak üç boyutlu kaynar su reaktör (BWR) modellemesinde bazı nötronik değerler incelendi. BWR modellemesinde reaktör koru 8x8 tipinde kare kafeslere ve her kare kafes kendi içinde 7x7 tipinde küçük kare kafeslere bölünerek tasarlandı. Bu çalışmada, yakıt çubuğu olarak % 0,02-0,1 oranlarında Neptünyum (Np) ve Amerisyum (Am) minör aktinitleri, yakıt zırhı olarak Zirkolay-2 (Zr-2), soğutucu olarak su kullanılarak 7x7 tipinde küçük kare kafesler oluşturuldu. 8x8 tipinde kare kafesler içine B4C kontrol çubukları haç şeklindeki bölgede yerleştirildi. BWR modellemesinde % 0,02-0,1 oranlarında Np ve Am yakıt çubukları ve Zr-2 yakıt zırhı için keff, fisyon enerjisi ve depolanan ısınma oranı nötronik değerleri hesaplandı. MCNPX-2.7.0 Monte Carlo metodu ve ENDF/B-VIII.0 nükleer veri kütüphanesi kullanılarak BWR sisteminin üç boyutlu modellemesi tasarlandı.

Kaynakça

  • [1] J. Zakova, J. Wallenius, "Multirecycling of Pu, Am and Cm in BWR," Ann. Nucl. Energy, 58, 255-267, 2013.
  • [2] J. Loberg, M. Österlung, J. Blomgren, K. Bejmer, "Neutron detection-based void monitoring in boiling water reactors," Nucl. Sci. Eng., 164, 69-79, 2010.
  • [3] J. Loberg, Novel Diagnostics and Computational Methods of Neutron Fluxes in Boiling Water Reactors, Digital Comprehensive Summaries of Uppsala Dissertations from The Faculty of Science and Technology 715, ISSN: 1651-6214, 2010.
  • [4] R. Fridstrom, "Response of The Gamma TIP Detectors in a Nuclear Boiling Water Reactor," UPTEC F10 042, ISSN: 1401-5757, 2010.
  • [5] K. Edsinger, K. L. Murty, "LWR pellet-cladding interactions: materials solutions to SCC," JOM, 53, 9-13, 2001.
  • [6] C. D. Williams, M. Marlowe, R. B. Adamson, S. B. Wisner, R. A. Rand, J. S. Armijo, "Zircaloy-2 lined zirkonium barrier fuel cladding," Twelfth International Symposium, ASTM STP 1295, 1996, pp. 676–694.
  • [7] C. Wan, X. Zou, L. Cao, H. Wu, "Covariance comparisons between ENDF/B-VII.I and ENDF/B-VIII.0 with application for the UAM-LWR exercises," Ann. Nucl. Energy, 138, 107-183, 2020.
  • [8] H. O. Wooten, "An application for streamlined and automated ENDF Cross Section Analysis and visualization (EXSAN)," Ann. Nucl. Energy, 129, 482-486, 2019.
  • [9] O. Kabach, A. Chetaine, A. Benchrif, "Processing of JEFF-3.3 and ENDF/B-VIII.0 and testing with critical benchmark experiments and TRIGA Mark II research reactor using MCNPX," Appl. Radiat. Isot., 150, 146-156, 2019.
  • [10] B. Şarer, A. Aydın, M. Günay, M. E. Korkmaz, E. Tel, "Calculations of neutron induced production cross-sections of 180,182,183,184,186W up to 20 MeV," Ann. Nucl. Energy, 36, 417-426, 2009.
  • [11] M. Günay, "Investigation of radiation damage in structural material of APEX reactor by using Monte Carlo Method," Ann. Nucl. Energy, 53, 59-63, 2013.
  • [12] H. W. Bertini, "Low-energy intranuclear cascade calculation," Phys. Rev., 131, 1801, 1963.
  • [13] H. W. Bertini, "Intranuclear-Cascade calculation of the secondary nucleon spectra from nucleon–nucleus interactions in the energy range 340 to 2900 MeV and comparisons with experiment," Phys. Rev., 188, 1711, 1969.
  • [14] Y. Yariv, Z. Fraenkel, "Intranuclear Cascade Calculation of High-Energy Heavy-Ion Interactions," Phys. Rev. C, 20, 2227, 1979.
  • [15] Y. Yariv, Z. Fraenkel, "Intranuclear Cascade Calculation of High Energy Heavy Ion Collisions: Effect of Interactions Between Cascade Particles," Phys. Rev. C, 24, 488, 1981.
  • [16] A. Boudard, J. Cugnon, S. Leray, C. Volant, "Intranuclear Cascade Model for a Comprehensive Description of Spallation Reaction Data," Phys. Rev. C, 66, 615, 2002.
  • [17] J. Cugnon, "Proton-Nucleus Interaction at High Energy," Nucl. Phys. A, 462, 751-780, 1987.
  • [18] J. Cugnon, C. Volant, S. Vuillier, "Improved Intranuclear Cascade Model for Nucleon-Nucleus Interactions," Nucl. Phys. A, 620, 475-509, 1997.
  • [19] S. G. Mashnik, V. D. Toneev, "MODEX – The Program for Calculation of The Energy Spectra of Particles Emitted in The Reactions of Pre-equilibrium and Equilibrium Statistical Decays," JINR P4-8417, 25, 1974.
  • [20] L. Dresner, "EVAP—a FORTRAN Program for Calculating The Evaporation of Various Particles from Excited Compound Nuclei," Report ORNL/TM-196, 1962.
  • [21] A. R. Junghans, M. Jong, H. G. Clerc, A. V. Ignatyuk, G. A. Kudyaev, K. H. Schmidt, "Projectile-Fragment Yields as a Probe for The Collective Enhancement in The Nuclear Level Density," Nucl. Phys. A, 629, 635-655, 1998.
  • [22] B. Şarer, S. Şahin, M. Günay, Y. Çelik, "Comparisons of The Calculations Using Different Codes Implemented in MCNPX Monte Carlo Transport Code for Accelerator Driven System Target," Fusion Sci. Technol., 61, 302-307, 2012.
  • [23] M. Günay, H. Kasap, "Neutronic investigation of the application of certain plutonium-mixed fluids in a fusion–fission hybrid reactor", Ann. Nucl. Energy, 63, 432–436, 2014.
  • [24] S. E. Ouahdani, H. Boukhal, L. Erradi, E. Chakir, M. Azahra, T. E. Bardouni, M. Makhloul, A. Ahmed, "A temperature effect analysis of the KRITZ-1 benchmark based on keff decomposition and using the JENDL-4.0 and ENDF/B-VII.1 libraries," Prog. Nucl. Energ., 109, 121-129, 2018.
  • [25] J. J. Duderstadt, L. J. Hamilton, Nuclear Reactor Analysis, John Wiley&Sons, Inc. 1976.
  • [26] Y. Liu, B. Kochunas, W. Martin, T. Downar, "Delayed fission energy effect on LWR normal operation and transients," Ann. Nucl. Energy, 128, 84–93, 2019.
  • [27] S. Şahin, B. Şarer, Y.Çelik, "Utilization of nuclear waste plutonium and thorium mixed fuel in candu reactors," Int. J. Energ. Res., 40, 1901–1907, 2016.
  • [28] B. Şarer, S. Şahin, Y. Çelik, M. Günay, "Evaluation of integral quantities in an accelerator driven system using different nuclear models implemented in the MCNPX Monte Carlo transport code," Ann. Nucl. Energy, 62, 382-389, 2013.
Toplam 28 adet kaynakça vardır.

Ayrıntılar

Birincil Dil Türkçe
Konular Metroloji,Uygulamalı ve Endüstriyel Fizik
Bölüm Makaleler
Yazarlar

Mehtap DÜZ 0000-0002-0445-1648

Yayımlanma Tarihi 31 Mayıs 2020
Yayımlandığı Sayı Yıl 2020 Cilt: 15 Sayı: 1

Kaynak Göster

IEEE M. DÜZ, “Bir Kaynar Su Reaktör Modellemesinde Np ve Am Yakıt Çubukları için Bazı Nötronik Değerlerin İncelenmesi”, Süleyman Demirel University Faculty of Arts and Science Journal of Science, c. 15, sy. 1, ss. 140–147, 2020, doi: 10.29233/sdufeffd.705690.