LEE, S.M.YORIYAZ, H.CABRAL, E.L.L.2022-12-202022-12-202022LEE, S.M.; YORIYAZ, H.; CABRAL, E.L.L. Radiation shielding for a nuclear fusion device with inertial electrostatic confinement. <b>Brazilian Journal of Radiation Sciences</b>, v. 10, n. 3A, p. 1-13, 2022. DOI: <a href="https://dx.doi.org/10.15392/2319-0612.2022.1997">10.15392/2319-0612.2022.1997</a>. Disponível em: http://repositorio.ipen.br/handle/123456789/33489.2319-0612http://repositorio.ipen.br/handle/123456789/33489In an inertial electrostatic confinement nuclear fusion device, IECF, thermal neutron population is created near the neutron shielding that is proportional to the fast neutrons generation rate; nevertheless, this proportionality varies with the experimental arrangement. Thus, to properly measure the fast neutron generation rate by the IECF device it is necessary to previously elaborate a suitable neutron transport model between the IECF device and the radiation shield, where the neutron detector will be located. This model is elaborated using the Monte Carlo N-Particle Code and the same is used to design the required radiation shield for the safe operation of the device.1-13openAccessshieldingradiation protectionthermonuclear reactionsinertial fusion driversmonte carlo methodneutronsArtigo de periódico3A1010.15392/2319-0612.2022.19970000-0001-6632-26920000-0003-4023-236Xhttps://orcid.org/0000-0003-4023-236XSem PercentilSem Percentil CiteScore