GEANT4 Kodunu Kullanarak Gama ve Nötron Radyasyonu için Koruyucu Yeni Laterit Tuğla Örneklerinin Geliştirilmesi ve Üretilmesi

Bu çalışmada, radyasyon zırhlamak için farlı yüzdelerde [silikon dioksit, krom oksit, alüminyum oksit, hematit, bizmut oksit, mangan oksit, baryum titanat oksit, titanyum oksit kalsiyum oksit gibi malzemeler içeren yüksek performanslı yeni tip tuğla numuneleri tasarlandı ve üretildi. Toplam makroskobik tesir kesit, ortalama serbest yol ve transmisyon sayıları gibi hızlı nötron zırhlama parametreleri, Monte Carlo Simulation Geant4 kodu kullanılarak hesaplandı. Nötron soğurma deneyleri 4.5 MeV enerji 241Am-Be hızlı nötron kaynağı ve BF3 gazlı nötron dedektörü kullanılarak yapıldı. Yeni tuğla örneklerinin radyasyon kalkanı kapasitesini belirlemek için elde edilen sonuçlar, parafin ve geleneksel beton ile karşılaştırıldı. Gama radyasyonu için kütle zayıflatma katsayısı ve yarı değer kalınlığı (HVL) gibi bazı etkileşim parametreleri WinXCom yazılımı kullanılarak hesaplandı, sonuçlar geleneksel ve basalt ağır beton ile karşılaştırıldı. Yeni tip tuğla numunelerinin hem nötron hem de gama radyasyonu için iyi zırhlama kapasitesi gösterdiği tespit edildi. Bu yeni tip tuğla numunelerinin, nükleer tıpta, radyoaktif atıkların depolanmasında ve nükleer enerji santrallerinde zırhlama malzemesi olarak kullanılabileceği belirlendi.

Anahtar Kelimeler:

Geant4, Gamma and Neutron, Laterite Brick, Shielding

Developed and Produced New Laterite Refractory Brick Samples Protective for Gamma and Neutron Radiation Using GEANT4 Code

In this study, high performance for radiation shielding, new type brick samples have been designed and produced, these containing in different percentages materials such as [silicon dioxide, chromium oxide, aluminium oxide, hematite, bismuth oxide, manganese oxide, barium titanate oxide, titanium oxide calcium oxide, nickel oxide, zirconium oxide, lead oxide)]. Fast neutron shielding parameters, such as total macroscopic cross section effect, mean free path and transmission number have been calculated by using Monte Carlo Simulation Geant4 code. Neutron absorbed dose experiments have been carried out by using 4.5 MeV energy 241Am-Be fast neutron source and BF3 gas neutron detector. The obtained results have been compared with paraffin and conventional concrete, to determine the radiation shielding capacity of new brick samples. Some interaction parameters for gamma radiation, such as the mass attenuation coefficient and half-value layer (HVL) have been calculated by using WinXCom software, the results have been compared with conventional and basalt heavy concrete. It is found that, the new type brick samples show good shielding capacity for both neutron and gamma radiation. These new type brick samples can use has been determined for shielding material, in nuclear medicine, in the storage of radioactive waste and nuclear power plants.

Keywords:

Geant4, Gama ve Nötron, Laterit Tuğla, Zırhlama,

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