Analysis for Radiation and Shielding Dose in Plasma Focus Neutron Source Using FLUKA

Abstract

Monte Carlo simulations have been performed for the attenuation of neutron radiation produced at Plasma focus (PF) devices through various shielding design. At the test site it will be fired with deuterium and tritium (D-T) fusion resulting in a yield of about 10 13 fusion neutrons of 14 MeV. This poses a radiological hazard to scientists and personnel operating the device. The goal of this paper was to evaluate various shielding options under consideration for the PF operating with D-T fusion. Shields of varying neutrons-shielding effectiveness were investigated using concrete, polyethylene, paraffin and borated materials. The most effective shield, a labyrinth structure, allowed almost 1,176 shots per year while keeping personnel under 20 mSV of dose. The most expensive shield that used, square shield with 100 cm concrete thickness on the walls and Borated paraffin along with borated polyethylene added outside the concrete allowed almost 15,000 shot per year.

Influence of Microwave Treatment on Properties of Concrete with Non-Cyclic Alkanes

“…Paraffin, in addition to materials such as water, graphite or other compounds which include a plurality of hydrogen and carbon atoms, is often used as shielding material. Alone or in combination with other materials, just such as concrete, usually as the outer layering [14,15,16]. Paraffin is also used as PCM (phase change material).…”