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Radiation Dosimetry in Cases of Normal and Emergency Situations

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Radiation Dosimetry in Cases of Normal and Emergency Situations Radiation Dosimetry in Cases of Normal and Emergency Situations A Thesis Submitted to Department of Physics Faculty of Science, Al Azhar University for The Degree of PhD. in Physics by Tarek Mahmoud Morsi M.Sc. (Physics, 2003) Radiation Protection Department, Nuclear Research Center, Atomic Energy Authority Under Supervision Emeritus Prof. M. I. El Gohary Emeritus Prof. M. A. Gomaa Prof. of Biophysics Prof. of Radiation Physics Al Azhar University Atomic Energy Authority Emeritus Prof. Samia M. Rashad Emeritus Dr. Eid M. Ali Prof. of Radiation Emergencies Lecturer of Radiation Physics Atomic Energy Authority Atomic Energy Authority 2010 Approval Sheet for Submission Ti tle of the PhD. Thesis Radiation Dosimetry in Cases of Normal and Emergency Situations Name of the Candidate Tarek Mahmoud Morsi Atomic Energy Authority This thesis has been approved for submission by the supervisors : Emeritus Prof. M. I. El Gohary Emeritus Prof. M. A. Gomaa Prof. of Biophysics Prof. of Radiation Physics Al Azhar University Atomic Energy Authority Emeritus Prof. Samia M. Rashad Emeritus Dr. Eid M. Ali Prof. of Radiation Emergencies Lecturer of Radiation Physics Atomic Energy Authority Atomic Energy Authority Acknowledgement First and above all, all thanks to ALLAH the Merciful, the Compassionate without his help. I couldn't finish this work. I wish to express my sincere thanks and gratitude to Professor Dr. Mohamed I. EL-Gohary, Prof. of Biophysics, faculty of science, Al- Azhar University and Professor Dr. Mohamed A. Gomaa, Prof. of Radiation Physics, Atomic Energy Authority (A.E.A) for their kind supervision, continuous encouragement and helps during the course of this work. I wish to introduce my great thanks to Professor Dr. Samia M. Rashad, Prof. of Radiation Emergencies, Atomic Energy Authority, for her interest and continuous effective help. I would like to thank Dr. Eid M. Ali, Lecturer of Radiation Physics, Atomic Energy Authority for his help during the course of this work. Thanks also to Head of Physics Department, Faculty of science, Al-Azhar University, Prof. Ismail Kashef for his care and help. Sincere thanks and gratitude are due to my colleagues in whole body counter unit for their continuous support, great efforts and help for providing me with the practical requirements of the work. Finally, thanks to Head of Radiation Protection Department, Nuclear Research Center, Atomic Energy Authority and the staff members and our colleagues for their assistance. Contents List of Tables VI List of Figures IX List of Abbreviations XI Summary XII Introduction and aim of the work XIX Published papers XXII Chapter 1 Literature Review 1.1 Ionizing radiation 1 1.2 Biological effects in human 1 1.3 Radiation Dosimetry 2 1.4 Radiation Quantities and Units 3 1.5 Comparison of radiological protection criteria 3 1.6 Exposure Situations 7 1.7 Type of Exposures 7 1.8 The principles of radiological protection 8 1.8.1 Source-related principles 9 1.8.2 Individual-related principle 10 1.9 Abnormal (Emergency) situations 10 1.10 Statistical summary of radiation accidents 13 1.11 Previous work 16 1.11-1 TLD Studies 16 1.11-2 Whole Body Counter Studies 21 Chapter 2 Physical Considerations 2.1 Exposure of Man to Radiation Sources 41 2.2 Modes of radiation exposure 45 2.3 Radiation Detection 50 I 2.3.1 Radiation detection by using TLD for external dosimetry 52 2.3.2 Radiation detection by using WBC for internal dosimetry 56 2.3.2.1 Direct method (in vivo counting) 57 2.3.2.2 WBC Measurement Geometry 59 2.3.2.3 Preparation of individuals for measurement 60 2.3.2.4 System Operation 60 2.3.3 Biokinetic model of Iodine 61 Chapter 3 Experimental Techniques 3.1 Measuring equipments for external dosimetry 64 3.1.1 TLD Reader-4000 64 3.1.2 Furnace 68 3.1.3 Radiation sources 68 3.2 Measuring Equipments for internal dosimetry 70 3.2.1 FASTSCAN (WBC) system 70 3.2.2 ACCUSCAN-II (WBC) system 74 3.2.3 Abacos Software 79 3.2.4 Transfer Phantom 80 3.2.5 Performance of Whole Body Counter 81 3.2.6 Body Build Index 84 3.2.7 Estimation of the annual effective dose from 40 K 85 3.2.8 Effective half life (T 1/2 eff ) 86 Chapter 4 Results 4.1 External Dosimetry 87 4.1.1 Calibration of TLD-Materials 87 II 4.1.2 Factors Affecting TL Performance 90 4.1.3 Dose distribution measurements by using TLD dosimeters 96 4.1.3.1 Dose distribution around radiotherapy unit shield 96 4.1.3.2 Dose rate assessment for cobalt irradiation unit 99 4.2 Internal Dosimetry 100 4.2.1 Internal Dosimetry by using FASTSCAN 100 4.2.2 Assessment of 40 K in human by using NaI(Tl) detectors. 108 4.2.2.1 Total body potassium content (TBK) and 40 K activity for individual males. 108 4.2.2.2 TBK content and 40 K activity for individual females. 120 4.2.3 Estimation of Intake 131 I by using WBC (Abnormal Situation) 125 4.2.3.1 Estimation of 131 I 128 4.2.3.2 WBC measurement for five contaminated suspicious individual workers (5 special cases) 135 4.3 Internal dosimetry by using ACCUSCAN II 136 4.3.4 Thyroid gland dose assessment for some occupational workers. 141 4.4 Accident Conditions and Emergency Response 143 4.4.1 Emergency Planning Categories 143 4.4.2 Radiation dose reconstruction in some radiological events in Egypt. 145 4.4.2.1 Meet Halfa Radiation Accident, in 2000 145 4.4.2.2 Transport incident associated with the radioactive material [ 99mTc], in 2004 162 4.4.2.3 Transport incident contained radioactive material (131 I). 164 III Chapter 5 Discussion 5 Introduction 170 5.1 Measurements of External Dosimetry 170 5.2 Internal Dosimetry 171 5.3 Normal Exposures 172 5.3.1 40 K Measurements by using FASTSCAN 172 5.4 Accidental Exposures 176 5.4.1 Dose rate distribution around radiotherapy unit 176 5.4.2 Dose rate assessment for Cobalt irradiation unit 177 5.4.3 Measurement of 131 I by using FASTSCAN 177 5.4.4 Thyroid dose assessment by using HPGe detector 179 5.5 Dose reconstruction calculations 180 5.5.1 Meet Halfa Radiation Accident, in 2000 180 5.5.2 Lessons Learned from Meet Halfa accident 183 5.5.3 Actions taken by the Egyptian national authorities after the occurrence of Meet Halfa radiation accident 185 5.5.4 Transport incident associated with the radioactive material ( 99mTc), in 2004 186 5.5.5 New drafted regulatory rule for safe transport of radioactive material 187 5.5.6 Checklist for safe transport of radioactive materials 187 5.5.7 Transport incident containing radioactive material, in 2008 188 Conclusions 190 Recommendations 192 References 194 IV Appendix 1 203 Appendix 2 210 Appendix 3 211 Arabic summary 1 V List of Tables 1.1 Comparison of protection criteria for the 1990 and the 2007 recommendations) 4 1.2 Summary of listed accidents/events by type 14 1.3 Summary of listed nuclear/radiological accidents/events by country 15 2.1 Radiation Detectors 51 2.2 Properties of the TLD materials, which are used in the field of dosimetry and radiation measurements 55 2.3 Relative concentrations for TL-sample by EDX 56 3.1 Temperature Profile of Heating Cycle 67 3.2 Dose rate mapping for Cs-137 source 68 4.1 Individual calibration for each TLD-100 dosimeter irradiated to dose 0.77 mSv by using Cs-137. 88 4.2 Individual calibration for each TLD-500 dosimeter irradiated to dose 0.77 mSv by using the same source. 89 4.3 Optimum Annealing Condition 92 4.4 TL dose response for TLD-100 samples. 94 4.5 TL dose response for TLD-500 samples. 95 4.6 Dose distribution around shield of a radiotherapy unit by using TLD-500, exposure time 98.4 s, and field area 10x11.5 cm 2. 97 4.7 Dose distribution around shield of a radiotherapy unit by using TLD-500, exposure time 98.4 s and field area 24x6 99 cm 2. 4.8 Dose rate at irradiation facility by using TLD-100 99 4.9 Energy calibration for NaI(Tl) detector. 101 4.10 Energy resolution for NaI(Tl) detectors. 105 4.11 Count rates of 40 K versus efficiency for WBC. 106 VI 4.12 MSA and MDA for WBC at 1.46 MeV. 108 4.13 Total body potassium content (K) and radioisotope ( 40 K) for individual males. 111 4.14 Total body potassium content (K) and radioisotope ( 40 K) for Females. 122 4.15 Characteristics of 131 I. 126 4.16 MSA and MDA for FASTSCAN at 364.5 KeV. 127 4.17 Measurements of activities and CED due to inhalation 131 I of workers. 130 4.18a Determination of activities measured and CED due to inhalation of 131 I. 131 4.18b Initial activities calculated and CED due to inhalation of 131 I. 132 4.19 CED for two patients. 133 4.20 Total body potassium 40 K for 5 individual. 135 4.21 Energy calibration for HPGe detector 136 4.22 Efficiency calibration curve for HPGe detector 138 4.23 MSA and MDA for ACCUSCAN II. 141 4.24 Committed dose equivalent of 131 I in thyroid gland for some workers. 143 4.25 Emergency planning categories 144 4.26 The estimated accumulated doses at distances and periods 192 for some persons exposed to Ir source. 159 4.27 Classification of categories for sources used in common 161 practices.
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