Neutron Shielding Design for Experiment Research of (n,γ) Reaction

HUANG Xing; HE Guozhu; CHENG Pinjing; ZHANG Qiwei; ZHOU Zuying

doi:10.11804/NuclPhysRev.32.02.208

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Volume 32 Issue 2

Jun. 2015

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Article Navigation > Nuclear Physics Review > 2015 > 32(2): 208-211

HUANG Xing, HE Guozhu, CHENG Pinjing, ZHANG Qiwei, ZHOU Zuying. Neutron Shielding Design for Experiment Research of (n,γ) Reaction[J]. Nuclear Physics Review, 2015, 32(2): 208-211. doi: 10.11804/NuclPhysRev.32.02.208

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HUANG Xing, HE Guozhu, CHENG Pinjing, ZHANG Qiwei, ZHOU Zuying. Neutron Shielding Design for Experiment Research of (n,γ) Reaction[J]. Nuclear Physics Review, 2015, 32(2): 208-211. doi: 10.11804/NuclPhysRev.32.02.208

Neutron Shielding Design for Experiment Research of (n,γ) Reaction

doi: 10.11804/NuclPhysRev.32.02.208

school of nuclear science and technology, University of South China, Hengyang 421001, Hunan, China;

Received Date: 1900-01-01
Rev Recd Date: 1900-01-01
Publish Date: 2015-06-20

Abstract

Neutron capture cross section can be measured by Gamma-ray Total Absorption Facility (GTAF) with high precision. To reduce the background of experiments, the neutron source must be collimated and shielded, and the neutrons scattered from the sample must be absorbed to minimise interference after they go into the detector. The shield, collimator and absorber were simulated and designed with MCNP code. Boron-ontaining polyethylene with 3% BC4 and lead are used as the materials for the neutron collimator and shield. The diameter of the collimating aperture is 13 mm, and the length of the collimator is 500 mm. After being collimated, the diameter of neutron beam plateau at the sample position is 21 mm. The neutron absorber is made of polyethylene and BC4, and the thickness of polyethylene shell and BC4 shell are 60 and 10 mm, respectively. The simulated result shows that neutrons scattered from the sample can decay 93.7% through the neutron absorber.
- neutron collimator,
- neutron shielding,
- transmittance,
- plateau of beam
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通讯作者: 陈斌, bchen63@163.com

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沈阳化工大学材料科学与工程学院沈阳 110142

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Neutron Shielding Design for Experiment Research of (n,γ) Reaction

doi: 10.11804/NuclPhysRev.32.02.208

school of nuclear science and technology, University of South China, Hengyang 421001, Hunan, China;

Received Date: 1900-01-01
Rev Recd Date: 1900-01-01
Publish Date: 2015-06-20

Key words:

Abstract: Neutron capture cross section can be measured by Gamma-ray Total Absorption Facility (GTAF) with high precision. To reduce the background of experiments, the neutron source must be collimated and shielded, and the neutrons scattered from the sample must be absorbed to minimise interference after they go into the detector. The shield, collimator and absorber were simulated and designed with MCNP code. Boron-ontaining polyethylene with 3% BC4 and lead are used as the materials for the neutron collimator and shield. The diameter of the collimating aperture is 13 mm, and the length of the collimator is 500 mm. After being collimated, the diameter of neutron beam plateau at the sample position is 21 mm. The neutron absorber is made of polyethylene and BC4, and the thickness of polyethylene shell and BC4 shell are 60 and 10 mm, respectively. The simulated result shows that neutrons scattered from the sample can decay 93.7% through the neutron absorber.

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