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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
Citation: 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
  • Received Date: 1900-01-01
  • Rev Recd Date: 1900-01-01
  • Publish Date: 2015-06-20
  • 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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Neutron Shielding Design for Experiment Research of (n,γ) Reaction

doi: 10.11804/NuclPhysRev.32.02.208

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.

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
Citation: 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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