MC simulation of a PGNAA system for on-line cement analysis

LOW ENERGY ACCELERATORS AND RADIATION APPLICATIONS

MC simulation of a PGNAA system for on-line cement analysis

YANG Jianbo，

TUO Xianguo，

LI Zhe，

MU Keliang，

CHENG Yi，

MOU Yunfeng

Nuclear Science and Techniques

Vol.21, No.4

pp.221-226

Published in print 20 Aug 2010

DOI：10.13538/j.1001-8042/nst.21.221-226

44900

A prompt gamma neutron activation analysis system with a ²⁵²Cf neutron source for on-line cement analysis has been simulated with the MCNP code. The results indicate that the optimum arrangement is a Bi shield of 20-mm thickness, a polyethylene moderator of 50-mm thickness, a source-to-sample distance of 70 mm, and cement samples of 1200 mm×600 mm×170 mm. To absorb thermal neutrons and suppress low-energy γ-rays, the optimum-sized sheets are 150 mm×7 mm Cd, and 150 mm×15 mm Pb.

Monte Carlo simulationPrompt γ neutron activation analysisModerator materialNeutron flux

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