Speaker
Mr
Ilia Urupa
(National Research Nuclear University MEPhI (Moscow Engineering Physics Institute))
Description
In this work, we calculated the parameters of the biological protection of the neutron generator NG-24 manufactured by FSUE VNIIA in order to ensure the radiation safety of medical personnel. The calculation was carried out using the Geant4 software package. Calculations were performed for materials such as polyethylene and boron polyethylene. Capacities of equivalent doses of neutron and gamma radiation at the borders of the simulated protection do not exceed the values specified in the main administrative documents on radiation safety.
Summary
As a result of the calculation, the following biological protection thicknesses were obtained (neutron flux is about 10 to 11 power neutrons per second) :
L1 (PE) = 250 cm,
L2 (BPE) = 300 cm,
for ordinary and boron polyethylene, respectively. This thicknesses gives us a permissible dose on the border of a protection. In terms of weight, this is about 100 tons, which is unacceptable for conventional medical institutions. Thus, it is necessary either to reduce the thickness of the protection and, accordingly, the removal of medical personnel over long distances, or the use of composite biological protection from both gamma and neutron radiation.
Primary authors
Mrs
Elena Ryabeva
(National Research Nuclear University MEPhI (Moscow Engineering Physics Institute))
Mr
Ilia Urupa
(National Research Nuclear University MEPhI (Moscow Engineering Physics Institute))
Ms
Polina Ponomareva
(National Research Nuclear University MEPhI (Moscow Engineering Physics Institute))
