Measurement and calculation of the neutron spectrum and gamma dosimetry of the fast neutron device at Xi’an Pulse Reactor

Shu-Huan Liu,Xin-Biao Jiang,Nan-Nan Liu,Guang-Ning Zhu,Da Li,Ji-Hong Zhang,Qing-Yu Yu

Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment（2008）

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摘要

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.

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关键词

Fast neutron facility,Neutron spectrum,Gamma dosimetry,TLD

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