Page 211 - 00. Complete Version - Progress Report IPEN 2014-2016
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Nuclear Science and Technology | Progress Report  211





               tillation, gross alpha and beta counting, and   Internal dosimetry: Routine
               thermoluminescent dosimetry are employed.
                                                              The workers that carry out activities in areas
               The Institutional PMRA has shown over the      where unsealed sources are handled are rou-
               years that the radiological environmental im-  tinely monitored to demonstrate that they
               pact of IPEN’s facilities is negligible, as the ef-  are receiving adequate protection from in-
               fective doses to members of the public are     ternal contamination. Direct measurements
               several orders of magnitude lower than the     of whole-body and thyroid contents provide
               recommended levels.                            an estimation of the radionuclide activity in-
                                                              corporated by the potentially exposed work-
                                                              ers. These measurements are carried out for
                                                              workers, trainees and visitors and are rou-
                                                              tinely performed by the In Vivo Monitoring
                                                              Laboratory, LMIV. The frequency of measure-
                                                              ments is defined by the Radioprotection Ser-
                                                              vice (SRP) and the Dose Calculation Group of
                                                              IPEN. For this purpose, LMIV are equipped with
                                                              two measurement systems: the whole body
                                                              counter, NaI(Tl) (8x4”), and the thyroid count-
                                                              er, NaI(Tl) (3x3”). The counting room internal
                                                              dimensions are 2.6 m x 1.7 m x 1.85 m and
                                                              the walls are made with 130 mm-thick steel
                                                              sheet lined with 5 mm of lead and 5 mm of
                                                              copper. The air is conditioned and the tem-
               Figure 14. The renewed sample preparation laborato-  perature maintained at 25ºC. The measure-
               ry for the characterization of radioactive effluents pro-  ment system is calibrated in energy and effi-
               duced by IPEN’s facilities, for the execution of the Institu-
               tional Environmental Radiological Monitoring Program.   ciency, with 152 241 60 sources of Eu, Am and
                                                              Co with gamma emissions between 59.54 and
                                                              1,408.08 keV, positioned within Alderson Re-
               Determination of radionuclides in              search Labs anthropomorphic phantom. The
               foodstuff and commodities                      background measurements spectrum is ob-
                                                              tained from workers that were not exposed
               Several analytical techniques are available and   occupationally. The concepts adopted in the
               offered in the form of providing services to the   HPS N13.30 Standard and proposed in ISO
               private sector. Available analyses include: de-  documents for standardization are used for
               termination of gross alpha and beta activities;   activity measurements. The dose calculation
               determination of natural and artificial gam-   follows the measurements of the activity in
               ma emitters; determination of uranium, tho-    excreta or in body tissues. The calculation of
               rium and radium isotopes; determination of     activity in body compartments and the com-
               vvvvvvvvvPb and 222Rn; determination of        mitted dose estimates are carried out with
               radionuclides in foodstuffs and commodities    the software “Activity and Internal Dose Es-
               imported and exported by Brazil; and deter-    timates”, AIDE. These calculations are based
               mination of 90Sr in foodstuffs and food com-   on the mathematical models recommended
               modities; and determination of 3H in water.    by the International Commission on Radio-
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