Page 32 - PR 2014 2016 03 Applications of Ionizing Radiations
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74   Application of Ionizing Radiations | Progress Report





               to obtain qualitative and quantitative data sys-  41 Ar was transferred, by the portable radiation
               tems, in physical and physicochemical studies   meter Teletector ® Probe 6150 AD-t/H.
               transfers. In the production of gaseous radio-
               isotopes used as tracers in industrial process   Sealed source production for
               measurements, argon-41 ( Ar) and krypton-79    gammagraphy and industrial
                                        41
                79
               ( Kr) have low reactivity with other chemi-    process control
               cal elements.  Ar is a transmitter range with
                            41
               high-energy (1.29MeV) and a high percentage    Radioactive sealed sources production for
               of this energy transformation (99.1%), resulting   radiography and industrial process control.
               in relatively small quantities required in rela-  The gamma writing is an important non-de-
               tion to the other, for an efficient detection, even   structive technique to analyze metallic compo-
               in large thicknesses components. Nowadays,     nents from small to large ones that need high
               the production of gaseous radioisotopes in     performance and security in operation. The
               nuclear research reactors is performed in small   non-existence of internal failures is checked
               quantities (batches), through quartz ampoules   by gamma rays radiography, because of its
                                           78
               containing natural gas  Ar or  Kr. In this sense,   great penetration characteristics that allow
                                     40
               the aim of this study is to develop an irradia-  obtaining the photographic record of failures.
               tion system for gaseous radioisotope produc-   This non-destructive analysis is used for qual-
               tion in continuous scale, applied in industrial   ity control of welded components in chemical,
               applications of emission tomography and flow   nuclear, and mechanical industries, such as
               measurement. The irradiation system may pro-   pipelines, turbines, reservoirs, and pressure
               duce  Ar with activity of 7.4x10 Bq (20Ci) per   vessels. According to the International Atomic
                    41
                                              11
               irradiation cycle, through the Reactor IEA-R1   Energy Agency (IAEA) information, the petro-
               with 4.5MW and average thermal neutron         chemical and chemical process industries are
               flux of 4.71x10  ncm -2s-1  to meet an existing   the mains users and beneficiaries of the radio-
                              13
               demand in NDT and inspections companies,       isotope technology. Radioisotope techniques
               and even needed by the Radiation Technolo-     are very competitive and are largely applied
               gy Centre, at IPEN/CNEN-SP. The irradiation    for troubleshooting and process analysis of
               system consists of an aluminium irradiation    technically complex, continuously operating
               capsule, transfer lines, needle valves, stripy   industrial plants. Due to this fact, the applica-
               connections, quick connectors, manometer,      tion of sealed sources becomes more diversi-
               vacuum system, dewar, lead shielding, storage
               and transport cylinders, among other compo-
               nents. The irradiation system was approved
               in the leakage and stability tests (bubble test,
               pressurization, evacuation and with leak de-
               tector equipment SPECTRON 600 T). In the
               experimental production, alanine dosimeters
               were distributed into various components of
               the irradiation system, obtaining 1.07x10 Bq
                                                       11
               (2.9Ci) of  Ar. In addition, exposure rates were
                        41
               determined in the lead shielding wall, in which
               the liquefied radioactive gas was concentrated,
               and in the storage and transport cylinders after   Figure 50. Laboratory Sealed Source Production.





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