LiH Reaktör Moderatör Malzemesi İçin Hadronik Etkileşimlerin Geant4 Benzetimi

Yıl 2016, Cilt: 11 Sayı: 2, 82 - 88, 02.12.2016

Mert Şekerci Veli Çapalı Hasan Özdoğan Abdullah Kaplan

Öz

LiH;
yoğunluğu, yüksek nötron yakalama tesir kesiti ve yüksek sıcaklıklarda
kullanılmasına imkân veren fiziksel-kimyasal özellikleri sayesinde nötron
moderasyonunda oldukça yaygın kullanılan bir moderatör malzemedir. Güçlü bir
benzetim programı olan GEANT4 ile LiH’in nötron moderatörü olarak kullanıldığı
bir ortam için düşük enerjili nötronların ve üretilen izotop-parçacıkların
hadronik etkileri araştırılmıştır. Ek olarak, LiH malzemesi için düşük nötron
akısında, enerji birikimi hesaplanmıştır

Anahtar Kelimeler

Nükleer reaktör, moderatör malzeme, hadronik etkileşimler, Geant4, lityumhidrit

Geant4 Simulation of Hadronic Interactions for the Reactor Moderator Material LiH

Öz

LiH
is one of the most common moderator materials for neutron moderation; due to
its high density, high neutron capture cross section and physical-chemical
properties that provides usage at elevated temperatures. Hadronic interactions
of low energetic neutrons and generated isotopes–particles have been investigated
for a situation in which LiH was used as a neutron moderator by using GEANT4,
which is a powerful simulation software. In addition, energy deposition along
LiH material has been calculated at low neutron flux

Anahtar Kelimeler

Nuclear reactor, moderator material, hadronic interactions, Geant4, lityumhydride

Kaynakça

• Doğan S. S., Çapalı V., Özdoğan H., Kaplan A., 2014. Eriyik Tuz Reaktörlerinde Yakıt Malzemesi Olarak Kullanılan Na Çekirdeğinin Üretim Tesir Kesiti Hesaplamaları, Süleyman Demirel University Journal of Science (e-journal), 9(2): 100-106.
• Tel E., 2010. Study on Some Structural Fusion Materials for (n,p) Reactions up to 30 MeV Energy, Journal of Fusion Energy, 29(4): 332-336.
• Aydın A., 2010. Pre-Equilibrium 3He-Emission Spectra at 62 MeV Proton Incident Energy, Journal of Fusion Energy, 29(5): 476-480.
• Sarpün İ.H., 2015. Double Differential Alpha, Proton and Deuteron Emission Cross Section Calculations for the Structural Fusion Materials 46,48Ti,Journal of Fusion Energy, 34(3): 592-597.
• Demir B., Sarpün İ.H., Kaplan A., Çapalı V., Aydın A., Tel E., 2015. Double Differential Cross Section and Stopping Power Calculations of Light Charged Particle Emission for the Structural Fusion Materials 50,52Cr, Journal of Fusion Energy, 34(4): 808-816.
• Tel E., Aydın A., 2012. Investigation of Lead Target Nuclei Used on Accelerator-Driven Systems for Tritium Production, Journal of Fusion Energy, 31(1): 73-78.
• Özdoğan H., Çapalı V., Kaplan A., 2015. Reaction Cross–Section, Stopping Power and Penetrating Distance Calculations for the Structural Fusion Material 54Fe in Different Reactions, Journal of Fusion Energy, 34(2): 379-385.
• Sahan M., Tel E., Sahan A., Kara A., Aydin A., Kaplan A., Sarpün İ. H., Demir B., Akca S., Yildiz E., 2014. Calculations of Double-Differential Neutron Emission Cross Sections for 9Be Target Nucleus at 14.2 MeV Neutron Energy, Journal of Fusion Energy, 34(3): 493-499.
• Sarpün İ. H., Aydın A., Kaplan A., Koca H., Tel E., 2014. Comparison of Fission Barrier and Level Density Models in (a,f) Reactions of Some Heavy Nuclei,Annals of Nuclear Energy, 70: 175-179.
• Kaplan A., Sarpün İ.H., Aydin A., Tel E., Çapalı V., Özdoğan H., 2015. (g,2n) Reaction Cross Section Calculations of Several Even–Even Lanthanide Nuclei Using Different Level Density Models, Physics of Atomic Nuclei, 78(1): 53-64.
• Mocko M., Daemen L. L., Harlt M. A., Huegle T., Muhrer G., 2010. Experimental study of potential neutron moderator materials, Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment,624(1): 173-179.
• Shpil'rain E.E., Yakimovich K.A., Medl'nikova T.N., Polishchuk A.Y., 1987. Thermophysical Properties of Lithium Hydride, Deuteride and Tritide and of Their Solutions with Lithium‬, New York: American Institute of Physics, USA, p. 213.
• Metropolis,N., Ulam,S., 1949. The Monte Carlo Method, Journal of the American Statistical Association, 44(2): 335-341.
• Agostinelli S; et al. Geant4 Colloboration, 2003. Geant4 - a simulation toolkit,Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 506(3): 250-303.
• Demir B., Kaplan A., Çapalı V., Özdoğan H., Sarpün İ. H., Aydın A., Tel E., 2015. Neutron Production Cross–Section and Geant4 Calculations of the Structural Fusion Material 59Co for (a,xn) and (g,xn) Reactions, Journal of Fusion Energy, 34(3): 636-641.
• Brun R., Rademakers F., 1997. ROOT: An object oriented data analysis framework, Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 389(1-2): 81-86.
• Geant4 Collaboration, “Geant4 User's Guide for Application Developers,” 2014. http://geant4.web.cern.ch/geant4 (Erişim Tarihi: 05/04/2016)
• Çapalı V., Şekerci M., Özdoğan H., Kaplan A., 2016. Reaction Cross Section Calculations in Neutron Induced Reactions and GEANT4 Simulation of Hadronic Interactions for the Reactor Moderator Material BeO, Suleyman Demirel University Journal of Natural and Applied Sciences, 20 (2): 161-166.