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Volume 13 (2018) : Issue 3, Mar

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The Journal of Engineering

Monte Carlo simulation of biological shielding parameters in PGNAA

Content Provider	IET Digital Library
Author	Yang, Jianbo Peng, Kexin Qiao, Yujie Zhang, Can Li, Rui Li, Zhen
Abstract	A prompt γ neutron activation analysis (PGNAA) facility based on a 252Cf spontaneous fission neutron was performed with the final goal of obtaining various optimised radiation protection design parameters. MCNP Monte Carlo code was used to simulate the lead (Pb) shield thickness on two sides of the sample chamber, and B4C, B2O3, LiOH, LiF, and borax were selected as neutron-absorbing materials that were simulated to determine optimal parameters for the optimal design of a biological multilayer composite shield. A series of calculations performed with the MCNP code indicated that the 5 cm thick Pb innermost layer of a biological shield rapidly reduced fast neutrons, and a moderation layer of 25 cm thick paraffin, 20 mm thick borax, and 2 mm thick B4C were selected as neutron-absorbing materials. The calculated biological shield protection parameters satisfied the requirements of the PGNAA facility used in the experiment.
Starting Page	457
Ending Page	460
Page Count	4
Volume Number	13
e-ISSN	17500443
Issue Number	Issue 4, Apr (2018)
Alternate Webpage(s)	https://digital-library.theiet.org/content/journals/mnl/13/4
Alternate Webpage(s)	https://digital-library.theiet.org/content/journals/10.1049/mnl.2017.0644
Journal	Micro & Nano Letters
Publisher Date	2018-04-01
Access Restriction	Open
Rights Holder	© The Institution of Engineering and Technology
Subject Keyword	252Cf Spontaneous Fission Neutron B2O3 B4C Biological Effects of Gamma-rays Biological Effects of Ionizing Radiations (UV, X-ray, Gamma-ray; Particle Radiation Effects) Biological Multilayer Composite Shield Biological Shielding Parameter Boron Compounds Composite Material Interfaces Lead Lead Shield Thickness LiF LiOH Lithium Compound MCNP Monte Carlo Code Moderation Layer Monte Carlo Method Monte Carlo Simulation MultiLayer Neutron Absorption Neutron Activation Analysis Neutron-absorbing Material Nuclear Chemical Analysis Optimised Radiation Protection Design Parameter Pb PGNAA PGNAA Facility Probability Theory Prompt Γ Neutron Activation Analysis Radiation Protection Radiation Protection And Dosimetry Sample Chamber Size 2 Mm to 25 Cm Spontaneous Fission Statistics Stochastic Linearised SCUC Thick Borax Thick Paraffin Thick Pb Innermost Layer
Content Type	Text
Resource Type	Article

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