Optimization study of a transportable neutron radiography system based on a 252CF neutron source
The purpose of this work is the optimization of a transportable thermal neutron radiography system. Neutrons are produced by a 50 mg 252Cf source. The design was optimized with respect to parameters related with thermal neutron radiography and shielding. Owning to the spec...
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| Autores principales: | , , , |
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| Formato: | article |
| Lenguaje: | EN |
| Publicado: |
D.Ghitu Institute of Electronic Engineering and Nanotechnologies
2011
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| Materias: | |
| Acceso en línea: | https://doaj.org/article/0a8ea8f7a3d04f5d810615a0e59e71b3 |
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| Sumario: | The purpose of this work is the optimization of a transportable thermal neutron
radiography system. Neutrons are produced by a 50 mg
252Cf source. The design was optimized
with respect to parameters related with thermal neutron radiography and shielding. Owning to
the special collimator design, it was possible to optimize the neutron radiography parameters,
while the use of advanced shielding materials reduced the weight and the volume of the unit. The
unit was compatible with the European Union Directive on ‘Restriction of Hazardous
Substances’ (RoHS) 2002/95/EC and imulated using the MCNPX code.
Keywords: Thermal neutron radiography, MCNP, RoHS Directive |
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