Development of neutron shielding for an inertial electrostatic confinement nuclear fusion device

dc.creatorLEE, SEUNG M.
dc.creatorYORIYAZ, HELIO
dc.creatorCABRAL, EDUARDO L.L.
dc.creatorINTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
dc.date2020-01-15T17:22:21Z
dc.date2020-01-15T17:22:21Z
dc.dateOctober 21-25, 2019
dc.date.accessioned2023-09-28T14:13:47Z
dc.date.available2023-09-28T14:13:47Z
dc.identifierhttp://repositorio.ipen.br/handle/123456789/30712
dc.identifier0000-0001-6632-2692
dc.identifier0000-0003-4023-236X
dc.identifier.urihttps://repositorioslatinoamericanos.uchile.cl/handle/2250/9000939
dc.descriptionThis work aims to develop a suitable neutron shielding for an Inertial Electrostatic Confinement Nuclear Fusion device (IECF). Neutrons are generated in the IECF device as results of nuclear fusion reactions and their detection is fundamental for the development of the IECF device, because experimental data is needed to perform efficiency analysis and model validation. Nevertheless, it is essential to moderate the neutrons down to the thermal state to make it possible to detect those using conventional detectors. Therefore, to properly measure the fast neutron generation rate by the IECF device it is necessary to previously elaborate a detailed neutron transport model between the IECF device and the radiation shielding, where the neutron detector will be located. In this work, a model is elaborated using the Monte Carlo N-Particle Code and is used to design the required radiation shielding for the device. Later, the same model will be used to determine the proportionality factor between the fast neutron generation in the IECF device and the thermal neutron population in the shielding.
dc.format5088-5095
dc.publisherAssocia????o Brasileira de Energia Nuclear
dc.rightsopenAccess
dc.subjectdose equivalents
dc.subjectdose rates
dc.subjectelectrostatics
dc.subjectfast neutrons
dc.subjecticf devices
dc.subjectinertial confinement
dc.subjectmonte carlo method
dc.subjectneutron flux
dc.subjectneutron transport
dc.subjectshielding
dc.subjectthermal neutrons
dc.titleDevelopment of neutron shielding for an inertial electrostatic confinement nuclear fusion device
dc.typeTexto completo de evento
dc.coverageI
dc.localRio de Janeiro


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