DocumentCode
469604
Title
Simulating neutron propagations with FLUKA, GEANT4 and MCNP
Author
Yeh, Yung-Shun ; Wang, Chung-Hsiang ; Liu, Hong-Ming ; Liu, Tsung-Che ; Lin, Guey-Lin
Author_Institution
Nat. Chiao Tung Univ., Hsinchu
Volume
3
fYear
2007
fDate
Oct. 26 2007-Nov. 3 2007
Firstpage
2016
Lastpage
2018
Abstract
We perform simulations on neutron transport properties for neutrons with energies less than 500 MeV. The simulation packages FLUKA, GEANT4 and MCNP are used. The neutron energy distributions and attenuation lengths, which are resulted from a mono-energetic initial neutron beam traversing a given thickness of medium, are presented.
Keywords
Monte Carlo methods; neutron spectra; neutron transport theory; nuclear engineering computing; FLUKA; GEANT4; MCNP; attenuation lengths; monoenergetic initial neutron beam; neutron energy distributions; neutron propagation; neutron spectra; neutron transport properties; simulation packages; Attenuation; Concrete; Detectors; Libraries; Medical treatment; Neutrons; Nuclear and plasma sciences; Packaging; Particle beams; Radiation safety;
fLanguage
English
Publisher
ieee
Conference_Titel
Nuclear Science Symposium Conference Record, 2007. NSS '07. IEEE
Conference_Location
Honolulu, HI
ISSN
1095-7863
Print_ISBN
978-1-4244-0922-8
Electronic_ISBN
1095-7863
Type
conf
DOI
10.1109/NSSMIC.2007.4436548
Filename
4436548
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