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Advances in Radiotherapy
            & Nuclear Medicine                                             Shielding exaggeration in medical linac bunkers



            (IMRT), and volumetric-modulated arc therapy (VMAT).   of  Physics  in Medicine and  Engineering Report  No.  75
            In recent years, IMRT and VMAT have increasingly   (IPEM 75).  The shielding evaluation and determination
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            replaced three-dimensional conformal radiotherapy.  were performed for the existing vault using the analytical
              Conventionally, it was believed that an ideal photon   equations listed in the International Atomic Energy
                                                                                                            18
            beam used in treatment planning should be uniform across   Agency Safety Reports Series No.  47 (IAEA SRS-47)
            the treatment field. This uniformity is obtained using a   and the National Council on Radiation Protection and
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            flattening filter (FF) positioned in the linear accelerator   Measurements Report No. 151 (NCRP 151).  Both primary
            (linac) head. However, the widespread adoption of   and secondary barriers were assessed, with a particular
            non-uniform beam distribution has challenged this   focus on primary barriers that are directly exposed to
            assumption. Removing the FF results in flattening filter-  the beam. The impact of applying the IDR criteria on
            free (FFF) beams, now widely used for stereotactic and   shielding design has not been extensively studied. In this
            non-stereotactic radiotherapy treatments. As a result,   work, the thicknesses of the primary barriers obtained
            advanced treatment techniques prefer FFF beams over FF   with and without adhering to the above-mentioned IDR
            beams. 1-6                                         criteria were analyzed in detail and evaluated in the
                                                               context of fundamental radiation protection principles,
              Numerous studies 3,4,7-12  have thoroughly examined the   with particular emphasis on the “optimization” principle.
            main  dosimetric  properties  of  FFF  beams,  the  precision   The necessary recommendations were proposed regarding
            of dose calculations, and the quality of treatment plans   using the IDR criteria in its current form or modifying its
            for IMRT with unflattened beams. The FFF beams exhibit   use to suit the working conditions in radiation therapy
            distinct  characteristics  compared  to standard  FF beams,   units without overestimating the barriers’ thicknesses. This
            specifically in terms of high dose rate and a profile shape   study represents a step-by-step, comprehensive, practical
            that is peaked along the beam’s central axis. Moreover,   guide for determining shielding requirements for a real
            removing the FF significantly lowers the leakage radiation   linac bunker, with detailed explanations for each step.
            from the treatment head and softens the photons’ energy
            spectrum. 13-16  Furthermore, since the FF is a source of   2. Methods
            photoneutrons, its removal reduces neutron production
            from the linac’s head.                             2.1. Bunker description and shielding upgrade
                                                               approach
              The main objective of the radiation protection program
            in medical linear accelerator facilities is to protect workers,   Figure 1 represents the linac’s bunker before and after the
            the general public, and the environment from the harmful   shielding upgrade. The existing primary barrier thickness
            effects of ionizing radiation (gamma rays and photo-  (1.35 m) is inadequate for 6 or 10 MV linacs. One of the
            neutrons)  transmitted  outside  the linac’s vault.  Thus,   primary barriers is adjacent to the public waiting area, that
            shielding requirements are defined by the dosimetric   is, fully occupied, and fortunately, there is enough space to
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            characteristics of the clinically applied MV photon beams   extend it using ordinary concrete (density = 2.35 g/cm ).
            – more precisely, by the beam modality used during   The same situation applied to the primary ceiling, and it
            treatment (FF or FFF). In all cases, shielding design should   is also possible to extend the ceiling’s shielding since the
            avoid  unnecessary  overestimation.  A  balanced  approach   bunker’s roof is dedicated to the linac’s chillers and the
            must be taken, considering both the actual shielding   hospital’s heating, ventilation, and air conditioning system.
            needs under normal operating working conditions and the   The other primary barrier is adjacent to the maze of
            associated construction cost.                      another bunker, that is, partially occupied, and the space
                                                               is  very  limited  for  implementing  any  concrete  shielding
              This study aims to present a case analysis evaluating
            the  shielding  requirements  for an  existing  Co-60   beyond this barrier. Therefore, the necessary shielding
                                                               extension will be partially implemented using ordinary
            radiotherapy bunker intended to adequately accommodate   concrete inside the bunker; the largest thickness available
            an Elekta Versa HD medical linear accelerator operating
            at 6 and 10 MV, with and without an FF. The shielding   for this internal extension is 0.5 m × 3.12 m. This internal
                                                               shielding extension is very advantageous to support the
            evaluation considers both a standard operating workload   ceiling’s shielding extension from a structural engineering
            (40 patients/day) and an overload (60 patients/day) of 50%   point of view. The remaining shielding extension will be
            for each accelerator energy. The final thicknesses of the   implemented using high-density material, such as iron,
            primary barriers were determined such that the expected   outside the bunker.
            instantaneous dose rate (IDR) behind the barriers does not
            exceed 7.5 µSv/h for FF mode and 20 µSv/h for FFF mode,   The  left  secondary  barrier  of the  bunker’s maze  is
            in accordance with the recommendations of the Institute   comparatively short and thin (0.95  m). This results in a


            Volume 3 Issue 2 (2025)                         40                        doi: 10.36922/ARNM025070007
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