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Design of a virtual model of a hand-held Germanium detector and a
    voxelized ICRP whole body phantom: A Monte Carlo study




                    Dr. Asm Sabbir Ahmed



           Human Monitoring Laboratory, Radiation Protection Bureau
                              Health Canada




                  HPS Conference, West Palm Beach, Florida, June 26   30, 2011
Acknowledgements




         Dr. Gary H Kramer
         Dr. Kurt Ungar
       Radiation Protection Bureau, Health Canada, 775 Brookfield Road, Ottawa, ON K1A 0K9, Canada


         Ben Kennedy
         Ron Keyser
       ORTEC Detectors & Electronics, AMETEK-AMT, 801 South Illinois Avenue, Oak Ridge, TN 37830, USA


         Dr. Glenn Well
       Cardiac Imaging, University of Ottawa Heart Institute, 40 Ruskin St., Ottawa, ON K1Y 4W7, Canada




A S Ahmed | Health Physics Conference, June 26   30, 2011                                                 Slide:2
Contents

       Introduction

                            Objectives
                            Importance
                            Back ground information

                Materials and Methodology

                                           Micro detectives     HPGe detector
                                           ICRP voxel phantom      design features
                                           Monte Carlo Model: Multi layer attenuating medium
                                           Monte Carlo Model: Voxel phantom with Micro Det

                              Results and Discussion

                                                               Micro detectives   Performance studied
                                                               Spectral Signatures   Multi layer attenuating medium
                                                               Spectral Signatures   Voxel phantom

                                                            Conclusion


A S Ahmed | Health Physics Conference, June 26   30, 2011                                                             Slide:3
Study Objectives




             Development of a Monte Carlo model with a hand held HPGe (High Purity
             Germanium) detector integrating with a voxelized whole body ICRP
             phantom


             Study characteristic signatures of medical radionuclide, distributed in voxel
             organ, as captured externally in the radiation detector




A S Ahmed | Health Physics Conference, June 26   30, 2011   Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:4
Study Importance
        Radiation Detection and Isotope Identification in Security Monitoring



       Correct identification of a radionuclide is important to discriminate the type:
      medical, industrial or malicious material.


        Each radionuclide produces a characteristic spectral signature with single or
      multiple peaks (depending on the radionuclide) and a compton tail (depending on
      the source organ attenuation and scattering).

        The conventional isotope identification algorithm follows the procedure of
      identifying energy peaks by spectral analysis. However, the screening personnel
      need standardized spectral signatues of medical radionuclides for decision making.


                  The proposed model will generate the characteristic signatures of
               medical radio nuclides, as distributed in the source organ of human body,
                                    captured in external detectors.

A S Ahmed | Health Physics Conference, June 26   30, 2011   Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:5
Introduction
        Medical Radio nuclides                   Types and Varieties

      Medical radionuclides are divided into two groups based on applications: (i) diagnostic (ii) radiotherapeutic.

                            Diagnostic application                                 Therapeutic applications
                                                               Types of emitters
                Beta or gamma      Positron       Auger Electron     Beta            Positron      Alpha      Auger Electron
                     131I            18F             111In           131I             64Cu         211At          77Br

                     111In            11C             123I           89Sr             66Ga        223Ra           111In

                     201Tl            15O             125I          153Sm                          225Ac          123I

                     89Sr             13N                           166Ho                         149Tb           125I

                     103Pb           82Rb                            90Y                          224Ra           67Ga

                     192Ir           68Ge                           177Lu                          212Bi          201Tl

                    153Sm            60Cu                           149Pm                          213Bi          51Cr

                     166Ho           64Cu                           199Au                         227Th          140Nd

                     99mTc           61Cu                           64Cu                          255Fm          195mPt

                      90Y            76Br                           186Re

                     175Yb           77Br                           188Re

                     166Dy           124I                           67Cu

                                    94mTc                          117mSn

                                      86Y                            32P

                                     89Zr                           165Dy

                                     66Ga                           105Rh

                                 68Ge  / 68Ga                  111Ag

                                      30P

                                     34mCl

                                     Source: PNNL document: 19294, 2010; Valkooovic 2006, J Phys

A S Ahmed | Health Physics Conference, June 26    30, 2011            Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:6
Introduction
        Medical Radionuclide and Radio pharmaceuticals

                         Properties and Function


      For clinical purpose, the radio nuclides are combined with pharmaceuticals before they
     are injected into the patient s body.


       The radio pharmaceuticals distribute in the body and accumulates in the target organ.


       The distribution of the radio pharmaceuticals inside, is imaged externally by detectors

      The radio pharmaceuticals excrete out of the body with a biologic half life and also
     undergo physical decay


       From security perspective, the clinical procedures where multiple radio nuclides are
     used in parallel, or in consecutive studies, create a false peak or false radio nuclide
     identification, resulting a false alarm.

A S Ahmed | Health Physics Conference, June 26   30, 2011   Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:7
Introduction
        Medical Radio nuclides                   Types and Varieties


                         Properties of diagnostic and therapeutic radio pharmaceuticals

                                                                    Types of radio pharmaceuticals
             Parameters
                                                             Diagnostic                                     Therapeutic
      Types of Emission               In general, pure gamma emitter; decay by                 The preferred mode of decay is
                                      either electron capture or isomeric                      pure beta-minus emission.
                                      transition


      Energy                          Ideal imaging energy range is 100 to 250                 No exact energy range; In
                                      keV                                                      general, Emax ³ 1 MeV


      Chemical reactivity             Ideal radio pharmaceutical for diagnostic                Therapeutic radio-
                                      imaging readily binds to a wide variety of               pharmaceuticals are very target
                                      compounds under physiological conditions.                specific


      Target-to-nontarget             Distinguish pathology from background;                   Target-to-nontarget is essentially
      ratio                           target : non-target ~ 5:1                                high.


      Effective half-life             Measured in hours                                        Measured in days
      Source: Nuclear Medicine, Henkin et. Al., 1996


A S Ahmed | Health Physics Conference, June 26    30, 2011           Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:8
Materials
        Micro Detective System


                                                            Portable, easy handling and operation

                                                            Perforated sealing against moisture, dust

                                                            Wireless communications

                                                            Visual, auditory and vibrating alarm

                                                            Built-in comprehensive nuclide data library
                                                            of more than 100 radioisotopes

                                                            Discrimination capability: legitimate sources
                                                            (e.g. medical or industrial radioisotopes) and
                                                            malicious radioisotopes (e.g. radiological
                                                            dispersal device)
     Micro-Detective®-HX
     ORTEC                                                  MicDet has 40 fold better energy resolution
     Oak Ridge, TN, US                                      (selectivity) than the nearest alternative



A S Ahmed | Health Physics Conference, June 26   30, 2011   Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:9
Materials
        ICRP voxel phantom
                                                                 Reference Male and Female: ICRP 110, 2009

                                                                 Constructed from medical images of real
                                                                 people

                                                                 Consistent with the organ specification given
                                                                 in ICRP 89, 2002

                                                                 The organ masses were adjusted to the ICRP
                                                                 data on the adult reference phantoms

                                                                 The female phantom was based on the CT
                                                                 data, 43-year old, height 167 cm and mass 59
                                                                 kg;- scaled to 163 cm and 60 kg (Ref. Fem: )

                                                                 The data set consist of total 346 slices; 174 (5
                                                                 mm) from head and trunk; 43 (20 mm) from
                                                                 hands & legs; each with 256´256 pixels.

                     ICRP female voxel
                                                                 The voxel size = 1.875´1.875´5 @ 17.6 mm3.
                         phantom

A S Ahmed | Health Physics Conference, June 26   30, 2011   Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:10
Methodology

        Monte Carlo Model of the detection system


                                                                         MCNPX was used [McnpX 2005]
                                                                        Pulse height analyzer (F8 tally) was
                                                                      used
                                                                        The histogram was binned at 1.0 keV
                                                                      energy window
                                                                        The source energy was varied over
                                                                      50 to 550 keV
                                                                        The minimum source to detector
                                                                      distance: 50 cm


                                                            A. Mount cup (Al)                E. Out contact (Ge(w/Li ions))
                                                            B. End cap to crystal gap        F. Hole contact (Ge(w/B ions))
                                                            C. Mount cup base (Al)           G. mount cup wall (Al)
                                                            D. End cap window (Al)           H. end cap wall (Al)

 The schematic diagram of the MicDet system                             I. Detector end radius=0.8 cm

A S Ahmed | Health Physics Conference, June 26   30, 2011     Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:11
Methodology

        Monte Carlo Model of the detection system               Detector performance

                                                                    The pulse height histogram was
                                                                   generated using the F8 tally of MCNPX.

                                                                    The histogram was binned with an
                                                                   energy window of 1.0 keV.

                                                                     The source energy was varied within
                                                                   the range of 50 to 550 keV.

                                                                     Attenuating medium, consecutive
                                                                   studies were performed by placing a
                                                                   point source (small sphere of radius 0.5
                                                                   cm) at different depths of a block of
                                                                   tissue equivalent material.

                                                                     The detector to source distance was
                                                                   varied from 50 to 1000 cm.

A S Ahmed | Health Physics Conference, June 26   30, 2011   Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:12
Methodology

        Monte Carlo Model of the detection system               Multilayer medium



                                                                                           The innermost
                                                                                          medium is a water tank


                                                                                           The single source
                                                                                          positioned at the centre
                                                                                          of water tank


                                                                                            Multiple point sources
                                                                                          were positioned
                                                                                          horizontally, near the
                                                                                          lateral ends.

             Multi-layer heterogeneous attenuating medium. The width of
                          medium is half the length (W = L/2).


A S Ahmed | Health Physics Conference, June 26   30, 2011   Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:13
Methodology

        Monte Carlo Model of the detection system               ICRP voxel phantom




                                                                                       Moritz view of the
                                                                                      ICRP voxel phantom
                                                                                        99mTc was distributed
                                                                                      in the liver and 131I
                                                                                      was distributed in the
                                                                                      thyroid
                                                                                        Three detectors
                                                                                      captured signatures
                                                                                      from three projections:
                                                                                      Right Lateral (RL), In
                                                                                      front and Left lateral
                                                                                      (LL).




A S Ahmed | Health Physics Conference, June 26   30, 2011   Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:14
Results and Discussion

        Micro Detective performance Characteristic




                                                                                         Efficiency decreases about
                                                                                         155% , when photon energy
                                                                                         goes down from 140 keV
                                                                                         (99mTc) to 364 keV(131I).


                                                                                         For 99mTc (E = 140 keV),
                                                                                         the detection efficiency
                                                                                         (source in air) decreased
                                                                                         117 fold when the source
                                                                                         was moved from 50 to 450
                                                                                         cm.




A S Ahmed | Health Physics Conference, June 26   30, 2011   Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:15
Results and Discussion

        Micro Detective performance Characteristic




 Point source in front of the detector. Detection                 The attenuation curves for a point source in
 efficiency decreases following inverse square of the             homogeneous tissue equivalent material. The
 distance.                                                        point source was moved along the detector axis.


A S Ahmed | Health Physics Conference, June 26   30, 2011   Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:16
Results and Discussion

        Micro Detective performance Characteristic




                                                                                                 The attenuation effect
                                                                                                 due to off-axis, point-
                                                                                                 source positions. The
                                                                                                 source-plane was
                                                                                                 embedded inside the
                                                                                                 tissue equivalent
                                                                                                 material at (a) 2.5 (b)
                                                                                                 5.0 (c) 7.5 and (d) 10
                                                                                                 cm depths.




A S Ahmed | Health Physics Conference, June 26   30, 2011   Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:17
Results and Discussion

        Spectral Signature - Micro Detective System                      Multi layer medium




                                                        For longer attenuating path,
                                                        some secondary peaks are
                                                        observed;
                                                        Both for 99mTc and 131I




A S Ahmed | Health Physics Conference, June 26   30, 2011          Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:18
Results and Discussion

        Spectral Signature - Micro Detective System                         Multi layer medium




                                                            The spectral signature for
                                                             isotopes 99mTc and 131I
                                                        For two concentration rates:


                                                                   Left: 50:50
                                                                  Right: 10:90




A S Ahmed | Health Physics Conference, June 26   30, 2011             Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:19
Results and Discussion

        Spectral Signature             Micro Detective System with Voxel phantom

                                                            Voxel phantom


                                                                  Top
                                                                          LL


                                                                        Front
                                                             RL




A S Ahmed | Health Physics Conference, June 26   30, 2011           Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:20
Results and Discussion

        Spectral Signature             Micro Detective System with Voxel phantom

                                                            Voxel phantom


                                                                  Top
                                                                          LL


                                                                        Front
                                                             RL




A S Ahmed | Health Physics Conference, June 26   30, 2011           Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:21
Conclusion

        Micro Detective Performance



          ¨ The Monte Carlo tool described in this presentation shows that, it is possible to
          generate characteristic spectral signatures for medical radio nuclides, distributed in the
          attenuating medium or human body, as captured externally in radiation detectors.

          ¨ The MicDet showed a significant difference in its detection efficiency over a range of
          50 to 550 keV energy.

          ¨ MicDet showed higher efficiency to detect 140 keV photons (emitted from 99mTc), in
          comparison to that for 364 keV (131I) for a given source to detector distance.

          ¨ During security screening, a detector with high efficiency is effective to stop
          someone, carrying a radionuclide in the body before the person reaches the security
          point. MicDet is less efficient (unable to detect signal), beyond 5 to 6 m distance.



A S Ahmed | Health Physics Conference, June 26   30, 2011   Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:22
Conclusion

        Characteristic Spectral Signatures of Medical Radio nuclides




          ¨ The characteristic signatures captured in the MicDet (HPGe) detectors for point
          sources, embedded inside a multi-layer attenuating medium showed differences in the
          Compton tails, as caused by different attenuating scheme.


          ¨ Radio nuclides distributed over the organ in an ICRP voxel phantom, can be
          assumed as typical to that may happen in patient s body. A validation study of the
          proposed model will be performed later.




A S Ahmed | Health Physics Conference, June 26   30, 2011   Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:23

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A S Ahmed Presentation in Health Physics Society Conference, 2011

  • 1. Design of a virtual model of a hand-held Germanium detector and a voxelized ICRP whole body phantom: A Monte Carlo study Dr. Asm Sabbir Ahmed Human Monitoring Laboratory, Radiation Protection Bureau Health Canada HPS Conference, West Palm Beach, Florida, June 26 30, 2011
  • 2. Acknowledgements Dr. Gary H Kramer Dr. Kurt Ungar Radiation Protection Bureau, Health Canada, 775 Brookfield Road, Ottawa, ON K1A 0K9, Canada Ben Kennedy Ron Keyser ORTEC Detectors & Electronics, AMETEK-AMT, 801 South Illinois Avenue, Oak Ridge, TN 37830, USA Dr. Glenn Well Cardiac Imaging, University of Ottawa Heart Institute, 40 Ruskin St., Ottawa, ON K1Y 4W7, Canada A S Ahmed | Health Physics Conference, June 26 30, 2011 Slide:2
  • 3. Contents Introduction Objectives Importance Back ground information Materials and Methodology Micro detectives HPGe detector ICRP voxel phantom design features Monte Carlo Model: Multi layer attenuating medium Monte Carlo Model: Voxel phantom with Micro Det Results and Discussion Micro detectives Performance studied Spectral Signatures Multi layer attenuating medium Spectral Signatures Voxel phantom Conclusion A S Ahmed | Health Physics Conference, June 26 30, 2011 Slide:3
  • 4. Study Objectives Development of a Monte Carlo model with a hand held HPGe (High Purity Germanium) detector integrating with a voxelized whole body ICRP phantom Study characteristic signatures of medical radionuclide, distributed in voxel organ, as captured externally in the radiation detector A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:4
  • 5. Study Importance Radiation Detection and Isotope Identification in Security Monitoring Correct identification of a radionuclide is important to discriminate the type: medical, industrial or malicious material. Each radionuclide produces a characteristic spectral signature with single or multiple peaks (depending on the radionuclide) and a compton tail (depending on the source organ attenuation and scattering). The conventional isotope identification algorithm follows the procedure of identifying energy peaks by spectral analysis. However, the screening personnel need standardized spectral signatues of medical radionuclides for decision making. The proposed model will generate the characteristic signatures of medical radio nuclides, as distributed in the source organ of human body, captured in external detectors. A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:5
  • 6. Introduction Medical Radio nuclides Types and Varieties Medical radionuclides are divided into two groups based on applications: (i) diagnostic (ii) radiotherapeutic. Diagnostic application Therapeutic applications Types of emitters Beta or gamma Positron Auger Electron Beta Positron Alpha Auger Electron 131I 18F 111In 131I 64Cu 211At 77Br 111In 11C 123I 89Sr 66Ga 223Ra 111In 201Tl 15O 125I 153Sm 225Ac 123I 89Sr 13N 166Ho 149Tb 125I 103Pb 82Rb 90Y 224Ra 67Ga 192Ir 68Ge 177Lu 212Bi 201Tl 153Sm 60Cu 149Pm 213Bi 51Cr 166Ho 64Cu 199Au 227Th 140Nd 99mTc 61Cu 64Cu 255Fm 195mPt 90Y 76Br 186Re 175Yb 77Br 188Re 166Dy 124I 67Cu 94mTc 117mSn 86Y 32P 89Zr 165Dy 66Ga 105Rh 68Ge / 68Ga 111Ag 30P 34mCl Source: PNNL document: 19294, 2010; Valkooovic 2006, J Phys A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:6
  • 7. Introduction Medical Radionuclide and Radio pharmaceuticals Properties and Function For clinical purpose, the radio nuclides are combined with pharmaceuticals before they are injected into the patient s body. The radio pharmaceuticals distribute in the body and accumulates in the target organ. The distribution of the radio pharmaceuticals inside, is imaged externally by detectors The radio pharmaceuticals excrete out of the body with a biologic half life and also undergo physical decay From security perspective, the clinical procedures where multiple radio nuclides are used in parallel, or in consecutive studies, create a false peak or false radio nuclide identification, resulting a false alarm. A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:7
  • 8. Introduction Medical Radio nuclides Types and Varieties Properties of diagnostic and therapeutic radio pharmaceuticals Types of radio pharmaceuticals Parameters Diagnostic Therapeutic Types of Emission In general, pure gamma emitter; decay by The preferred mode of decay is either electron capture or isomeric pure beta-minus emission. transition Energy Ideal imaging energy range is 100 to 250 No exact energy range; In keV general, Emax ³ 1 MeV Chemical reactivity Ideal radio pharmaceutical for diagnostic Therapeutic radio- imaging readily binds to a wide variety of pharmaceuticals are very target compounds under physiological conditions. specific Target-to-nontarget Distinguish pathology from background; Target-to-nontarget is essentially ratio target : non-target ~ 5:1 high. Effective half-life Measured in hours Measured in days Source: Nuclear Medicine, Henkin et. Al., 1996 A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:8
  • 9. Materials Micro Detective System Portable, easy handling and operation Perforated sealing against moisture, dust Wireless communications Visual, auditory and vibrating alarm Built-in comprehensive nuclide data library of more than 100 radioisotopes Discrimination capability: legitimate sources (e.g. medical or industrial radioisotopes) and malicious radioisotopes (e.g. radiological dispersal device) Micro-Detective®-HX ORTEC MicDet has 40 fold better energy resolution Oak Ridge, TN, US (selectivity) than the nearest alternative A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:9
  • 10. Materials ICRP voxel phantom Reference Male and Female: ICRP 110, 2009 Constructed from medical images of real people Consistent with the organ specification given in ICRP 89, 2002 The organ masses were adjusted to the ICRP data on the adult reference phantoms The female phantom was based on the CT data, 43-year old, height 167 cm and mass 59 kg;- scaled to 163 cm and 60 kg (Ref. Fem: ) The data set consist of total 346 slices; 174 (5 mm) from head and trunk; 43 (20 mm) from hands & legs; each with 256´256 pixels. ICRP female voxel The voxel size = 1.875´1.875´5 @ 17.6 mm3. phantom A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:10
  • 11. Methodology Monte Carlo Model of the detection system MCNPX was used [McnpX 2005] Pulse height analyzer (F8 tally) was used The histogram was binned at 1.0 keV energy window The source energy was varied over 50 to 550 keV The minimum source to detector distance: 50 cm A. Mount cup (Al) E. Out contact (Ge(w/Li ions)) B. End cap to crystal gap F. Hole contact (Ge(w/B ions)) C. Mount cup base (Al) G. mount cup wall (Al) D. End cap window (Al) H. end cap wall (Al) The schematic diagram of the MicDet system I. Detector end radius=0.8 cm A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:11
  • 12. Methodology Monte Carlo Model of the detection system Detector performance The pulse height histogram was generated using the F8 tally of MCNPX. The histogram was binned with an energy window of 1.0 keV. The source energy was varied within the range of 50 to 550 keV. Attenuating medium, consecutive studies were performed by placing a point source (small sphere of radius 0.5 cm) at different depths of a block of tissue equivalent material. The detector to source distance was varied from 50 to 1000 cm. A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:12
  • 13. Methodology Monte Carlo Model of the detection system Multilayer medium The innermost medium is a water tank The single source positioned at the centre of water tank Multiple point sources were positioned horizontally, near the lateral ends. Multi-layer heterogeneous attenuating medium. The width of medium is half the length (W = L/2). A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:13
  • 14. Methodology Monte Carlo Model of the detection system ICRP voxel phantom Moritz view of the ICRP voxel phantom 99mTc was distributed in the liver and 131I was distributed in the thyroid Three detectors captured signatures from three projections: Right Lateral (RL), In front and Left lateral (LL). A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:14
  • 15. Results and Discussion Micro Detective performance Characteristic Efficiency decreases about 155% , when photon energy goes down from 140 keV (99mTc) to 364 keV(131I). For 99mTc (E = 140 keV), the detection efficiency (source in air) decreased 117 fold when the source was moved from 50 to 450 cm. A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:15
  • 16. Results and Discussion Micro Detective performance Characteristic Point source in front of the detector. Detection The attenuation curves for a point source in efficiency decreases following inverse square of the homogeneous tissue equivalent material. The distance. point source was moved along the detector axis. A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:16
  • 17. Results and Discussion Micro Detective performance Characteristic The attenuation effect due to off-axis, point- source positions. The source-plane was embedded inside the tissue equivalent material at (a) 2.5 (b) 5.0 (c) 7.5 and (d) 10 cm depths. A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:17
  • 18. Results and Discussion Spectral Signature - Micro Detective System Multi layer medium For longer attenuating path, some secondary peaks are observed; Both for 99mTc and 131I A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:18
  • 19. Results and Discussion Spectral Signature - Micro Detective System Multi layer medium The spectral signature for isotopes 99mTc and 131I For two concentration rates: Left: 50:50 Right: 10:90 A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:19
  • 20. Results and Discussion Spectral Signature Micro Detective System with Voxel phantom Voxel phantom Top LL Front RL A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:20
  • 21. Results and Discussion Spectral Signature Micro Detective System with Voxel phantom Voxel phantom Top LL Front RL A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:21
  • 22. Conclusion Micro Detective Performance ¨ The Monte Carlo tool described in this presentation shows that, it is possible to generate characteristic spectral signatures for medical radio nuclides, distributed in the attenuating medium or human body, as captured externally in radiation detectors. ¨ The MicDet showed a significant difference in its detection efficiency over a range of 50 to 550 keV energy. ¨ MicDet showed higher efficiency to detect 140 keV photons (emitted from 99mTc), in comparison to that for 364 keV (131I) for a given source to detector distance. ¨ During security screening, a detector with high efficiency is effective to stop someone, carrying a radionuclide in the body before the person reaches the security point. MicDet is less efficient (unable to detect signal), beyond 5 to 6 m distance. A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:22
  • 23. Conclusion Characteristic Spectral Signatures of Medical Radio nuclides ¨ The characteristic signatures captured in the MicDet (HPGe) detectors for point sources, embedded inside a multi-layer attenuating medium showed differences in the Compton tails, as caused by different attenuating scheme. ¨ Radio nuclides distributed over the organ in an ICRP voxel phantom, can be assumed as typical to that may happen in patient s body. A validation study of the proposed model will be performed later. A S Ahmed | Health Physics Conference, June 26 30, 2011 Introduction-> Materials & Methodology-> Results-> Conclusion | Slide:23