Epoxy Based Metal And Metal Oxide Doped New Composite Neutron And Gamma Radiation Moderator Material

Year 2019, Volume: 12 Issue: 3, 1442 - 1453, 31.12.2019

Bünyamin Aygün

https://doi.org/10.18185/erzifbed.544340

Cited By: 2

Abstract

In this
study, five different composite shield materials were developed and
produced.  Epoxy resin based different
proportions, materials such as [chromium oxide (Cr₂O₃),
lithium florür (LiF), nickel oxide (NiO), bismuth oxide (Bi₂O₃),
manganese oxide (MnO), copper oxide (CuO), titanium oxide (TiO₂),
cobalt oxide (CoO), gadolinium oxide (Gd₂O₃), selit (CaWO₄),
iron oxide (Fe₂O₃), lead oxide (PbO)] were used on
production. The GEANT4 code of the Monte
Carlo simulation program was used in determining mixing ratios. The total
macroscopic cross section, mean free path and transmission neutron number were
determined for fast neutron radiation by using GEANT4 simulation code. The mass
attenuation coefficient and half-value layer (HVL) were calculated for gamma
radiation by using WinXCom software. Experimental absorbed dose measurement was
carried out and in these measurements ²⁴¹Am-Be neutron source with
74 GBq activity which average neutron energy is approximately 4.5 MeV and BF₃
gas detector were used.  Both simulation
and experimental measurements were compared with paraffin, conventional
concrete. It was found that the new composite shielding material absorbed
radiation much better than these reference materials. It has been suggested
that this new radiation shielding composite material can be used in areas such
as nuclear medicine, transport and storage of radioactive waste, nuclear power
plants and as shield material for both neutron and gamma radiation. 

Keywords

Neutron and gamma radiation, epoxy, GEANT4, shielding, metal oxide

Epoksi Bazlı Metal Ve Metal Oksit Katkılı Yeni Kompozit Nötron Ve Gamma Radyasyon Moderatör Malzemesi

Abstract

Bu çalışmada beş farklı komposit zırh malzemesi geliştirildi ve üretildi.
Üretimlerde epoksi reçinesi taban malzeme olarak farklı özelliklere sahip [krom
oksit (Cr₂O₃), lityum florür (LiF), nikel oksit (NiO),
bizmut oksit (Bi₂O₃), manganez oksit (MnO), bakır oksit
(CuO), titanyum oksit (TiO₂), kobalt oksit (CoO), gadolinyum oksit
(Gd₂O₃), şelit (CaWO₄), demir oksit (Fe₂O₃),
kurşun oksit (PbO)] gibi malzemeler kullanılmıştır.

Karışım oranları Monte Carlo Simülasyon
programının GEANT4 kodu kullanılarak belirlenmiştir. Hızlı nötronlar için
Toplam makroskopik tesir kesiti, ortalama serbest yol ve geçen nötron sayısı
GEANT4 simülasyon kodu kullanılarak belirlendi. WinXCom yazılımı kullanılarak gamma radyasyonu için kütle zayıflama
katsayısı ve yarı değer kalınlıkları (HVL) hesaplandı. Deneysel absorbtion doz ölçümleri yapıldı ve bu ölçümlerde ortalama nötron
enerjisinin yaklaşık 4.5 MeV, 74 GBq aktiviteye sahip ²⁴¹Am-Be
nötron kaynağı ve BF₃ gazlı dedektör kullanıldı. Hem simülasyon hem de deneysel ölçümler, geleneksel beton ve parafin ile
karşılaştırıldı. Yeni kompozit zırh
malzemelerinin bu referans malzemelerden çok daha iyi radyasyon emdiği tespit
edildi. Bu yeni radyasyon zırh kompozit malzemelerin
nükleer tıpta, radyoaktif atıkların taşınması ve depolanmasında ve nükleer
santral gibi alanlarda, hem nötron hem de gama radyasyonu için kalkan malzemesi
olarak kullanılabileceği önerildi.

Keywords

Nötron ve gama radyasyonu, , epoksi, , GEANT4, , zırhlama, metal oksit

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