Title of article
Measurement and calculation of the neutron spectrum and gamma dosimetry of the fast neutron device at Xi’an Pulse Reactor
Author/Authors
Liu، نويسنده , , Shu-Huan and Jiang، نويسنده , , Xin-Biao and Liu، نويسنده , , Nan-Nan and Zhu، نويسنده , , Guang-Ning and Li، نويسنده , , Da and Zhang، نويسنده , , Jihong and Yu، نويسنده , , Qing-Yu، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2008
Pages
6
From page
361
To page
366
Abstract
The neutron spectrum and neutron fluence of a fast neutron device at Xi’an Pulse Reactor were measured with multiple foil activation method and calculated with Monte Carlo technique in the paper. Thermo-luminescence detector (TLD) (7LiF(Mg,Ti)-1007M) is used to measure gamma dosimetry of the device. The experimental result proves that the goal of the design is achieved.
Keywords
Gamma dosimetry , TLD , neutron spectrum , Fast neutron facility
Journal title
Nuclear Instruments and Methods in Physics Research Section A
Serial Year
2008
Journal title
Nuclear Instruments and Methods in Physics Research Section A
Record number
2210077
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