Irradiation system for production of gaseous radioisotopes used as tracers in industrial process measurements
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2018
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Progress in Nuclear Energy
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Resumo
The use of radioisotopes as radiotracers is considered the most important in diagnosing operation and troubleshooting
of industrial process plants in chemical and petrochemical companies. They are used in analytical
procedures to obtain qualitative and quantitative data systems, in physical and physicochemical studies transfers.
In the production of gaseous radioisotopes used as tracers in industrial process measurements, argon-41
(41Ar) and krypton-79 (79Kr) stand out because each has low reactivity with other chemical elements. 41Ar is a
transmitter range with high-energy (1.29 MeV) and a high percentage of this energy transformation (99.1%),
resulting in relatively small quantities required in relation to the other, for an efficient detection, even in large
thicknesses components. Nowadays, the production of gaseous radioisotopes in nuclear research reactors is
performed in small quantities (batches), through quartz ampoules containing natural gas 40Ar or 78Kr. In this
sense, the aim of this study is to develop an irradiation system for gaseous radioisotope production in continuous
scale, applied in industrial applications of emission tomography and flow measurement. The irradiation system
may produce 41Ar with activity of 7.4×1011 Bq (20 Ci) per irradiation cycle, through the Reactor IEA-R1 with
4.5MW and average thermal neutron flux of 4.71×1013 ncm−2s−1 to meet an existing demand in NDT and
inspections companies, and even needed by the Radiation Technology Centre, at IPEN/CNEN-SP. The irradiation
system consists of an aluminium irradiation capsule, transfer lines, needle valves, ringed connections, quick
connectors, manometer, vacuum system, dewar, lead shielding, storage and transport cylinders, among other
components. The irradiation system was approved in the leakage and stability tests (bubble test, pressurization,
evacuation and with leak detector equipment SPECTRON 600 T). In the experimental production obtaining
1.07×1011 Bq (2.9 Ci) of 41Ar, alanine dosimeters were distributed into various components of the irradiation
system. In addition, exposure rates were determined in the lead shielding wall, in which the liquefied radioactive
gas was concentrated, and in the storage and transport cylinders after 41Ar was transferred by the portable
radiation meter Teletector® Probe 6150 AD-t/H.
Como referenciar
CARDOZO, N.X.; OMI, N.M.; AMBIEL, J.J.; FEHER, A.; NAPOLITANO, C.M.; SOMESSARI, S.L.; CALVO, W.A.P. Irradiation system for production of gaseous radioisotopes used as tracers in industrial process measurements. Progress in Nuclear Energy, v. 107, p. 10-16, 2018. DOI: 10.1016/j.pnucene.2018.04.010. Disponível em: http://repositorio.ipen.br/handle/123456789/28933. Acesso em: 26 Apr 2024.
Esta referência é gerada automaticamente de acordo com as normas do estilo IPEN/SP (ABNT NBR 6023) e recomenda-se uma verificação final e ajustes caso necessário.