Neutron radiation dose calculations from composite neutron shield of the on-line coal analyzer

Li, Xiang-long; Cheng, Dao-wen; Liu, Lin-mao
May 2016
Journal of Radioanalytical & Nuclear Chemistry;May2016, Vol. 308 Issue 2, p425
Academic Journal
When the width of the on-line coal analyzer and the yield of the D-T neutron generator both meet the requirements, the neutron radiation dose shielded by any hydrogen-rich material is higher than the acceptable maximum dose for radiation worker (0.01 mSv/h). To decrease the neutron radiation dose, the double-layer material composed of copper-nickel alloy and boron-polyethylene is used in the analyzer. When the alloy is 41 cm thick, boron-polyethylene is 14 cm thick, the concentration of nickel is 20.00 % and the concentration of boron is 1.00 %, the neutron radiation dose is 0.0086 mSv/h.


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