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
fDate :
Oct. 26 2007-Nov. 3 2007
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;
Conference_Titel :
Nuclear Science Symposium Conference Record, 2007. NSS '07. IEEE
Conference_Location :
Honolulu, HI
Print_ISBN :
978-1-4244-0922-8
Electronic_ISBN :
1095-7863
DOI :
10.1109/NSSMIC.2007.4436548
