Simulations of neutron transport at low energy: A comparison between GEANT and MCNP

被引：13
|
作者：
Colonna, N
Altieri, S
机构：
[1] Ist Nazl Fis Nucl, Sez Bari, I-70126 Bari, Italy
[2] Sezione Ist Nazl Fis Nucl, I-27100 Pavia, Italy
[3] Dipartimento Fis Teorica & Nucl, I-27100 Pavia, Italy
来源：
HEALTH PHYSICS | 2002年 / 82卷 / 06期
关键词：
Monte Carlo; neutrons; attenuation; dose;
D O I：
10.1097/00004032-200206000-00012
中图分类号：
X [环境科学、安全科学];
学科分类号：
08 ; 0830 ;
摘要：
The use of the simulation tool LEANT for neutron transport at energies below 20 MeV is discussed, in particular with regard to shielding and dose calculations. The reliability of the GEANT/MICAP package for neutron transport in a wide energy range has been verified by comparing the results of simulations performed with this package in a wide energy range with the prediction of MCNP-4B, a code commonly used for neutron transport at low energy. A reasonable agreement between the results of the two codes is found for the neutron flux through a slab of material (iron and ordinary concrete), as well as for the dose released in soft tissue by neutrons. These results justify the use of the GEANTA-MICAP code for neutron transport in a wide range of applications, including health physics problems.
引用
收藏
页码：840 / 846
页数：7
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