Design of portable shield for neutron sources using MCNP Computer Code
نویسندگان
چکیده
منابع مشابه
The comparison between simple and advanced shielding materials for the shield of portable neutron sources
Background: Monte Carlo simulations play a vital role in the calculation of the necessary shielding both for neutrons and photons. Advanced and simple shielding materials against neutron and gamma rays were compared by simulation using the MCNB4B Monte Carlo code. The simulations were carried out for the three common neutron sources, namely the 252Cf, the 241Am/Be and the DD neutron generator w...
متن کاملthe comparison between simple and advanced shielding materials for the shield of portable neutron sources
background: monte carlo simulations play a vital role in the calculation of the necessary shielding both for neutrons and photons. advanced and simple shielding materials against neutron and gamma rays were compared by simulation using the mcnb4b monte carlo code. the simulations were carried out for the three common neutron sources, namely the 252cf, the 241am/be and the dd neutron generator w...
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Neutron Generators (NG) are used as a neutron source for different applications. During recent years, major efforts are underway to develop a high yield compact NG. In this way, radiation protection aspects need to be considered during the operation of these high yield NGs. In this paper the neutron effective dose of a NG operator has been calculated using MCNPX Monte Carlo code. The results sh...
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In this study, a flexible composite shield with a combination of polyethylene, tungsten and boron carbide has been designed and constructed for neutron-gamma mixed fields. For this purpose, theoretical studies were conducted using the multi-purpose MCNPX Code. According to the results of simulation studies, a multi-purpose composite was constructed using a combination of a solid phase of boron ...
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ژورنال
عنوان ژورنال: Arab Journal of Nuclear Sciences and Applications
سال: 2018
ISSN: 1110-0451
DOI: 10.21608/ajnsa.2018.2256.1021