The “neutron channel design”—A method for gaining the desired neutrons | Zendy

Guang Hu | Zendy; Hesuan Hu | Zendy; Shuang Wang | Zendy; Zhenchao Pan | Zendy; Qinggang Jia | Zendy; Mingfei Yan | Zendy

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The “neutron channel design”—A method for gaining the desired neutrons

Author(s) -

Guang Hu,

Hesuan Hu,

Shuang Wang,

Zhenchao Pan,

Qinggang Jia,

Mingfei Yan

Publication year - 2016

Publication title -

aip advances

Language(s) - English

Resource type - Journals

SCImago Journal Rank - 0.421

H-Index - 58

ISSN - 2158-3226

DOI - 10.1063/1.4972203

Subject(s) - neutron , beryllium , neutron moderator , neutron temperature , materials science , neutron source , neutron detection , monte carlo method , nuclear engineering , nuclear physics , neutron cross section , physics , engineering , statistics , mathematics

The neutrons with desired parameters can be obtained after initial neutrons penetrating various structure and component of the material. A novel method, the “neutron channel design”, is proposed in this investigation for gaining the desired neutrons. It is established by employing genetic algorithm (GA) combining with Monte Carlo software. This method is verified by obtaining 0.01eV to 1.0eV neutrons from the Compact Accelerator-driven Neutron Source (CANS). One layer polyethylene (PE) moderator was designed and installed behind the beryllium target in CANS. The simulations and the experiment for detection the neutrons were carried out. The neutron spectrum at 500cm from the PE moderator was simulated by MCNP and PHITS software. The counts of 0.01eV to 1.0eV neutrons were simulated by MCNP and detected by the thermal neutron detector in the experiment. These data were compared and analyzed. Then this method is researched on designing the complex structure of PE and the composite material consisting of PE, lead and zirconium dioxide

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