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Using Gamma Cameras to Assess Internal Contamination from Intakes of Radioisotopes

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Using Gamma Cameras to Assess Internal Contamination from Intakes of Radioisotopes Using Gamma Cameras to Assess Internal Contamination from Intakes of Radioisotopes Prepared by R. Anigstein, R. H. Olsher, and D. A. Loomis S. Cohen & Associates 1608 Spring Hill Road Vienna, Virginia 2218 Under Subcontract Number 30-06166-01 TKC Integration Services, LLC 6628 Brynhurst Drive Tucker, Georgia 30084 Prepared for Centers for Disease Control and Prevention National Center for Environmental Health Division of Environmental Hazards and Health Effects Radiation Studies Branch Under Contract Number 200-2006-15696 Phillip Green Project Officer January 17, 2010 Contents Page Preface. v 1 Instructions to Nuclear Medicine Technologists..................................... 1 1.1 Introduction............................................................. 1 1.2 Preliminary Steps........................................................ 1 1.2.1 Preparation of Nuclear Medicine Facility................................. 1 1.2.2 Setting up the Gamma Camera. ........................................ 1 1.2.3 Preparing Patient.................................................... 3 1.3 Performing Assessment. .................................................. 3 1.3.1 Preliminary Screening................................................ 3 1.3.2 Positioning Patient................................................... 4 1.3.3 Acquiring Counts................................................... 10 1.4 Calculating Intakes and Doses............................................. 11 1.4.1 Calculating Count Rates. ............................................ 11 1.4.2 Calculating Intake. ................................................. 11 1.4.3 Example Calculation of Intake. ....................................... 12 1.4.4 Calculating Doses. ................................................. 13 1.5 Using Other Models of Gamma Cameras..................................... 14 2 Calculating Intakes and Doses Using Assess. ..................................... 15 2.1 Quick-Reference Guide to Assess. ......................................... 15 2.2 Interpretation of Results.................................................. 18 2.2.1 High Count Rates................................................... 18 2.2.2 Accuracy of Model. ................................................ 19 3 Technical Description of Assess Program......................................... 20 3.1 Installation Notes. ...................................................... 20 3.2 Modules. ............................................................. 20 3.3 Folder Structure. ....................................................... 20 3.4 Calculation of Intakes and Doses........................................... 21 3.4.1 Adults............................................................ 21 3.4.2 Pre-Adults: 15 Years and Older....................................... 22 3.4.3 Children Under Age 15.............................................. 23 Appendix A. Calibration Factors for Converting Count Rates to Intakes. A-1 Appendix B. Cumulative Effective Dose at Selected Times after Intake.. B-1 References. R-1 ii Tables Page 1. Primary Set of Energy Windows for Siemens e.cam Gamma Camera.................... 2 2. Alternate Set of Energy Windows for Siemens e.cam Gamma Camera.. 2 3. Energy Windows of Philips SKYLight Gamma Camera.............................. 2 4. Threshold Exposure Rates at 1 m from Patients with Internal Radioactive Contamination. 4 5. Height and Weight of Reference Individual........................................ 9 6. Lung Absorption Types. ..................................................... 12 A-1. f1 Values Used in DCAL Calculations....................................... A-1 A-2. Inhaled Activity of Type M 60Co vs. Count Rate (Bq/kcpm)...................... A-2 A-3. Inhaled Activity of Type S 60Co vs. Count Rate (Bq/kcpm).. A-4 A-4. Inhaled Activity of Type F 90Sr vs. Count Rate (Bq/kcpm)....................... A-6 A-5. Inhaled Activity of Type S 90Sr vs. Count Rate (Bq/kcpm)....................... A-8 A-6. Inhaled Activity of Type F 131 I vs. Count Rate (Bq/kcpm). ..................... A-10 A-7. Inhaled Activity of Type F 137Cs vs. Count Rate (Bq/kcpm)..................... A-12 A-8. Inhaled Activity of Type F 192Ir vs. Count Rate (Bq/kcpm)...................... A-14 A-9. Inhaled Activity of Type M 192Ir vs. Count Rate (Bq/kcpm)..................... A-16 A-10. Inhaled Activity of Type S 192Ir vs. Count Rate (Bq/kcpm)..................... A-18 A-11. Inhaled Activity of Type M 241Am vs. Count Rate (Bq/kcpm).. A-20 A-12. Ingested Activity of 60Co vs. Count Rate (Bq/kcpm).......................... A-22 A-13. Ingested Activity of 90 Sr vs. Count Rate (Bq/kcpm). ......................... A-24 A-14. Ingested Activity of 131I vs. Count Rate (Bq/kcpm)........................... A-26 A-15. Ingested Activity of 137 Cs vs. Count Rate (Bq/kcpm). ........................ A-28 A-16. Ingested Activity of 192Ir vs. Count Rate (Bq/kcpm).......................... A-30 A-17. Ingested Activity of 241Am vs. Count Rate (Bq/kcpm)......................... A-32 B-1. Cumulative Effective Dose Following Intake of 60 Co (Sv/Bq). B-2 B-2. Cumulative Effective Dose Following Intake of 90Sr (Sv/Bq). B-3 B-3. Cumulative Effective Dose Following Intake of 131I (Sv/Bq).. B-4 B-4. Cumulative Effective Dose Following Intake of 137Cs (Sv/Bq). B-5 B-5. Cumulative Effective Dose Following Intake of 192Ir (Sv/Bq). B-6 B-6. Cumulative Effective Dose Following Intake of 241Am (Sv/Bq). B-7 iii Figures Page 1. Pediatric Patient with Philips SKYLight. ......................................... 4 2. Infant–Siemens e.cam......................................................... 5 3. Infant–Philips SKYLight. ..................................................... 5 4. 1-y-old–Siemens e.cam........................................................ 5 5. 1-y-old–Philips SKYLight..................................................... 5 6. 5-y-old–Siemens e.cam........................................................ 6 7. 5-y-old–Philips SKYLight..................................................... 6 8. 10-y-old–Siemens e.cam....................................................... 6 9. 10-y-old–Philips SKYLight.................................................... 6 10. 15-y-old–Siemens e.cam...................................................... 7 11. 15-y-old–Philips SKYLight................................................... 7 12. Adult Male–Siemens e.cam. .................................................. 8 13. Adult Male–Philips SKYLight................................................. 8 14. Adult Female–Siemens e.cam.................................................. 8 15. Adult Female–Philips SKYLight............................................... 8 iv PREFACE During the past three years, S. Cohen and Associates, sponsored by the Centers for Disease Control and Prevention, prepared a series of reports which is being expanded, revised, and reissued under the title “Use of Radiation Detection, Measuring, and Imaging Instruments to Assess Internal Contamination from Intakes of Radionuclides.” Part I of the series (Anigstein et al. 2007a) described a study to evaluate radiation detection and imaging systems commonly found in hospitals to determine their suitability for rapidly scanning individuals for internal contamination, and to develop recommendations regarding their potential use. That report describes the measurement of count rates from single discrete radioactive sources of 60 Co, 137 Cs, 192 Ir, and 241 Am, using a Philips AXIS gamma camera, an Atomlab thyroid uptake system, and a Ludlum waste monitor. Part II (Anigstein et al. 2007b) extended the earlier investigation by using realistic anthropomorphic phantoms to study the responses of four instruments to five radionuclides distributed in the lungs. The experimental measurements were performed on sources in the lung region of a Rando Phantom—an anthropomorphic phantom that contains a human skeleton embedded in a tissue-equivalent urethane rubber. Count rates from each of five radionuclides—60 Co, 90 Sr, 137 Cs, 192 Ir, and 241 Am—were measured on a Siemens e.cam gamma camera, an Atomlab thyroid probe, a Ludlum survey meter, and a Ludlum waste monitor. In a preliminary analysis, the Los Alamos MCNPX (Monte Carlo N Particle eXtended) computer code was used to calculate calibration factors that relate count rates on these instruments to lung burdens of each of the five nuclides. A mathematical model of each of the instruments was constructed, using engineering drawings and other data obtained from the manufacturers. This model was combined with an MCNP model of a Rando Phantom, constructed from CT scans of this phantom (Wang et al. 2004). The combined model was used to simulate the response of each instrument to sources in the phantom. The agreement between the calculated and measured responses validated the MCNP models of the four instruments. Part III (Anigstein et al. 2007c) extended the investigations to the Philips SKYLight camera. The study was narrowed to three of the five radionuclides reported in part II: 60 Co, 137 Cs, and 241 Am. This study encompassed measurements and corresponding MCNP simulations of sources of the three nuclides located in the lung region of a Rando Phantom. In addition, measurements and simulations were carried out of the source capsules in air. The agreement between the calculated and measured responses validated the MCNP model of this instrument. Part IV (Anigstein et al. 2010) extended the earlier investigations to the response of the Philips
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