Investigation of Neutron Attenuation Properties for the Different
Density Materials
Journal Name:
- Süleyman Demirel Üniversitesi Fen Dergisi
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Keywords (Original Language):
Author Name | University of Author | Faculty of Author |
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Abstract (2. Language):
The generation of high-intensity radiation fields in the accelerators, shield design is made to attenuation permissible levels of radiation dose. For determination of shield material, thicknesses, weight, installation and maintenance costs as well as radiation attenuation properties are taken into consideration such factors. Effective radiation for shielding is neutrons in proton accelerators and shield design is made for neutrons. Concrete, soil and iron are widely used as a shield material.
In this paper, the different density of the shielding materials (soil, standard concrete, iron) were selected to determine for the minimum thickness of the side wall for shielding design of proton accelerator. The thickness of the shielding is obtained by a simulation with the Monte Carlo Code FLUKA.
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Abstract (Original Language):
Yuksek yogunluklu radyasyon alanlarinin olu§tugu hizlandiricilarda, radyasyon seviyesini izin verilen doz degerlerine zayiflatmak igin zirh tasarimi yapilir. Zirhin belirlenmesinde, radyasyon zayiflatma ozellikleriyle birlikte kalinligi, agirligi, kurulum ve bakim maliyeti gibi faktorler de goz onunde bulundurulur. Proton hizlandincilarinda, zirhlama igin etkin olan radyasyon notronlardir ve zirh tasarimi notronlara gore yapilir. Zirh maddesi olarak genellikle beton, toprak ve gelik kullanilir.
Bu gali§mada, hizlandirici zirh tasariminda gerekli minimum yan duvar zirh kalinliklarini belirlemek igin farkli yogunluklarda (toprak, standart beton, demir) zirh maddeleri segildi. Zirh kalinliklari, FLUKA Monte Carlo kodu ile belirlendi.
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