Research and development of ABS filament's capability for gamma and neutron radiation shielding
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Date
2023
Authors
Journal Title
Journal ISSN
Volume Title
Publisher
Sinop Üniversitesi
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info:eu-repo/semantics/openAccess
Abstract
Radyasyon, neredeyse tüm nükleer uygulamalar için ana güvenlik sorunudur ve canlıları ve uygulamaların çevresindeki malzemeleri korumak için kontrol altında tutulmalıdır. Bu bağlamda, radyasyon koruma malzemeleri araştırılmış ve nükleer teknolojilerde kullanıl-mıştır. Radyasyon kullanım alanına, türüne ve enerjisine bağlı olarak malzeme seçimi ya-pılmalıdır. Polimer malzemeler, kimyasal inertlik, direnç, esneklik, mukavemet ve düşük maliyet gibi üstün özelliklerinden dolayı radyasyon koruma uygulamalarında tercih edil-mektedir. Bu tezde, 3D baskıda yaygın olarak kullanılan ABS (Akrilonitril Bütadien Stiren) termoplastiklerin Er2O3 ve Gd2O3 katkı maddeleri ile zenginleştirilmesi sonucu elde edilen gama ve nötron koruma özellikleri kapsamlı bir şekilde incelenmiştir. Değişik malzeme kalınlıkları ve radyasyon enerjileri üzerinde, deneysel, teorik ve simülasyon yöntemlerini kapsayan çok yönlü bir yaklaşım kullanarak, bu modifiye termoplastiklerin gama ve nöt-ron radyasyonunu zayıflatma etkinliği araştırılmıştır. Ayrıca, üretilen malzemelerin mikro-yapıları, yapısal bütünlüğü sağlamak amacıyla incelenmiştir. Araştırma, döküm ve 3D baskı olmak üzere iki farklı üretim yönteminin karşılaştırmalı bir analizini içermektedir. Üretilen örnekler, üretim tekniğine ve içerdiği nano oksit bileşiklerine göre sistematik ola-rak kodlandı. Gama radyasyonu zayıflatmasını ölçmek için çeşitli radyoaktif nokta kay-nakları kullanıldı ve HPGe dedektör sistemi, XCOM, EpiXS gibi teorik ve FLUKA ve GE-ANT4 gibi araçlar ile birlikte çalışıldı. Eş zamanlı olarak, nötron zayıflatma özellikleri teo-rik ve FLUKA ve GEANT4 simülasyon hesaplamaları ile değerlendirildi. Mikroyapıları incelemek için SEM / EDS ve Termal inceleme için TGA analizi yapıldı ve her örnek için en uygun koruma malzemesi belirlendi. Titiz analizler ve değerlendirmelerle, bu tez, özel-likle 3D baskı teknolojisi ile üretilen özelleştirilebilir ve karmaşık yapılar gerektiren uygu-lamalar için radyasyon koruma malzemelerinin geliştirilmesi ve optimizasyonuna katkıda bulunmaktadır.
Radiation is a fundamental safety concern for nearly all nuclear applications, requiring careful control to protect living organisms and surrounding materials. In this context, radi-ation shielding materials have been researched and utilized in nuclear technologies. Mate-rial selection must be based on the radiation's application, type, and energy. Polymer mate-rials are preferred for radiation protection applications due to their superior properties such as chemical inertness, durability, flexibility, strength, and cost-effectiveness. In this thesis, the gamma and neutron shielding properties of ABS (Acrylonitrile Butadiene Styrene) thermoplastics commonly used in 3D printing have been comprehensively investigated through enrichment with Er2O3 and Gd2O3 additives. Employing a versatile approach encompassing experimental, theoretical, and simulation methods, the efficacy of these modified thermoplastics in attenuating gamma and neutron radiation has been studied across different material thicknesses and radiation energies. Furthermore, the microstruc-tures of the produced materials have been examined to ensure structural integrity. The re-search includes a comparative analysis of two different production methods: casting and 3D printing. The manufactured samples were systematically labeled based on the produc-tion technique and the nano-oxide compounds they contained. Various radioactive point sources were utilized to measure gamma radiation attenuation, and the HPGe detector sys-tem, along with theoretical tools like XCOM and EpiXS, as well as simulations such as FLUKA and GEANT4, were employed. Simultaneously, neutron attenuation properties were evaluated through theoretical calculations and FLUUKA and GEANT4 simulations. SEM/EDS analysis was conducted to examine microstructures, and TGA analysis was per-formed for thermal characterization, ultimately determining the optimal shielding material for each sample. Through rigorous analysis and evaluations, this thesis contributes to the development and optimization of radiation shielding materials, particularly for applications requiring customization and complex structures, such as those produced using 3D printing technology.
Radiation is a fundamental safety concern for nearly all nuclear applications, requiring careful control to protect living organisms and surrounding materials. In this context, radi-ation shielding materials have been researched and utilized in nuclear technologies. Mate-rial selection must be based on the radiation's application, type, and energy. Polymer mate-rials are preferred for radiation protection applications due to their superior properties such as chemical inertness, durability, flexibility, strength, and cost-effectiveness. In this thesis, the gamma and neutron shielding properties of ABS (Acrylonitrile Butadiene Styrene) thermoplastics commonly used in 3D printing have been comprehensively investigated through enrichment with Er2O3 and Gd2O3 additives. Employing a versatile approach encompassing experimental, theoretical, and simulation methods, the efficacy of these modified thermoplastics in attenuating gamma and neutron radiation has been studied across different material thicknesses and radiation energies. Furthermore, the microstruc-tures of the produced materials have been examined to ensure structural integrity. The re-search includes a comparative analysis of two different production methods: casting and 3D printing. The manufactured samples were systematically labeled based on the produc-tion technique and the nano-oxide compounds they contained. Various radioactive point sources were utilized to measure gamma radiation attenuation, and the HPGe detector sys-tem, along with theoretical tools like XCOM and EpiXS, as well as simulations such as FLUKA and GEANT4, were employed. Simultaneously, neutron attenuation properties were evaluated through theoretical calculations and FLUUKA and GEANT4 simulations. SEM/EDS analysis was conducted to examine microstructures, and TGA analysis was per-formed for thermal characterization, ultimately determining the optimal shielding material for each sample. Through rigorous analysis and evaluations, this thesis contributes to the development and optimization of radiation shielding materials, particularly for applications requiring customization and complex structures, such as those produced using 3D printing technology.
Description
Keywords
Nükleer Mühendislik, Nuclear Engineering, Polimer Bilim ve Teknolojisi
