How Do We Compare Activity and Dose? How Many Picocuries in a Chest X-Rays?
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Radiation Risk in Perspective
PS010-1 RADIATION RISK IN PERSPECTIVE POSITION STATEMENT OF THE HEALTH HEALTH PHYSICS SOCIETY* PHYSICS SOCIETY Adopted: January 1996 Revised: August 2004 Contact: Richard J. Burk, Jr. Executive Secretary Health Physics Society Telephone: 703-790-1745 Fax: 703-790-2672 Email: [email protected] http://www.hps.org In accordance with current knowledge of radiation health risks, the Health Physics Society recommends against quantitative estimation of health risks below an individual dose of 5 rem1 in one year or a lifetime dose of 10 rem above that received from natural sources. Doses from natural background radiation in the United States average about 0.3 rem per year. A dose of 5 rem will be accumulated in the first 17 years of life and about 25 rem in a lifetime of 80 years. Estimation of health risk associated with radiation doses that are of similar magnitude as those received from natural sources should be strictly qualitative and encompass a range of hypothetical health outcomes, including the possibility of no adverse health effects at such low levels. There is substantial and convincing scientific evidence for health risks following high-dose exposures. However, below 5–10 rem (which includes occupational and environmental exposures), risks of health effects are either too small to be observed or are nonexistent. In part because of the insurmountable intrinsic and methodological difficulties in determining if the health effects that are demonstrated at high radiation doses are also present at low doses, current radiation protection standards and practices are based on the premise that any radiation dose, no matter how small, may result in detrimental health effects, such as cancer and hereditary genetic damage. -
Absorbed Dose in Radioactive Media Outline Introduction Radiation Equilibrium Charged-Particle Equilibrium Limiting Cases
Outline • General dose calculation considerations, Absorbed Dose in Radioactive absorbed fraction Media • Radioactive disintegration processes and associated dose deposition – Alpha disintegration Chapter 5 – Beta disintegration – Electron-capture transitions F.A. Attix, Introduction to Radiological – Internal conversion Physics and Radiation Dosimetry • Summary Introduction Radiation equilibrium • We are interested in calculating the absorbed dose in a. The atomic composition radioactive media, applicable to cases of of the medium is – Dose within a radioactive organ homogeneous – Dose in one organ due to radioactive source in another b. The density of the organ medium is • If conditions of CPE or RE are satisfied, dose homogeneous c. The radioactive source calculation is straightforward is uniformly distributed • Intermediate situation is more difficult but can be d. No external electric or handled at least in approximations magnetic fields are present Charged-particle equilibrium Limiting cases • Emitted radiation typically includes both • Each charged particle of a given type and photons (longer range) and charged energy leaving the volume is replaced by an particles (shorter range) identical particle of the same energy entering • Assume the conditions for RE are satisfied the volume • Consider two • Existence of RE is sufficient condition for CPE limited cases based • Even if RE does not exist CPE may still exist on the size of the (for a very large or a very small volume) radioactive object 1 Limiting cases: small object Limiting -
Toolkit 1: Energy Units and Fundamentals of Quantitative Analysis
Energy & Society Energy Units and Fundamentals Toolkit 1: Energy Units and Fundamentals of Quantitative Analysis 1 Energy & Society Energy Units and Fundamentals Table of Contents 1. Key Concepts: Force, Work, Energy & Power 3 2. Orders of Magnitude & Scientific Notation 6 2.1. Orders of Magnitude 6 2.2. Scientific Notation 7 2.3. Rules for Calculations 7 2.3.1. Multiplication 8 2.3.2. Division 8 2.3.3. Exponentiation 8 2.3.4. Square Root 8 2.3.5. Addition & Subtraction 9 3. Linear versus Exponential Growth 10 3.1. Linear Growth 10 3.2. Exponential Growth 11 4. Uncertainty & Significant Figures 14 4.1. Uncertainty 14 4.2. Significant Figures 15 4.3. Exact Numbers 15 4.4. Identifying Significant Figures 16 4.5. Rules for Calculations 17 4.5.1. Addition & Subtraction 17 4.5.2. Multiplication, Division & Exponentiation 18 5. Unit Analysis 19 5.1. Commonly Used Energy & Non-energy Units 20 5.2. Form & Function 21 6. Sample Problems 22 6.1. Scientific Notation 22 6.2. Linear & Exponential Growth 22 6.3. Significant Figures 23 6.4. Unit Conversions 23 7. Answers to Sample Problems 24 7.1. Scientific Notation 24 7.2. Linear & Exponential Growth 24 7.3. Significant Figures 24 7.4. Unit Conversions 26 8. References 27 2 Energy & Society Energy Units and Fundamentals 1. KEY CONCEPTS: FORCE, WORK, ENERGY & POWER Among the most important fundamentals to be mastered when studying energy pertain to the differences and inter-relationships among four concepts: force, work, energy, and power. Each of these terms has a technical meaning in addition to popular or colloquial meanings. -
Nuclear Radiation 1. an Atom Contains Electrons, Protons and Neutrons
Nuclear Radiation 1. An atom contains electrons, protons and neutrons. Which of these particles a) are outside the nucleus b) are uncharged c) have a negative charge d) are nucleons e) are much lighter than the others? 2. Complete the table below. Name Symbol Charge What is it? Alpha particle β -1 Gamma ray An electromagnetic wave 3. How is an ionised material different from a material that is not ionised? National 5 Physics: Waves & Radiation 1 Absorption of Radiation 1. The figure below shows a Geiger tube used to detect radiation from a radioactive source. thick lead plate 0 4 2 5 start counter stop ON OFF reset Geiger tube radioactive source The following measurements were made using the apparatus above. Counts in 300 seconds Readings Average 1 No source present 102 94 110 2 Source present at fixed distance from tube a) No lead plate present 3466 3420 3410 b) Thick lead plate present 105 109 89 c) Aluminium sheet in place of the 1834 1787 1818 thick lead sheet a) Complete the table by calculating the average readings. b) Why are the readings on each line not the same? c) What can you say from the table about the effect on the radiation of: i. The lead plate? ii. The aluminium plate? d) Why is it possible to say from the readings that: i. gamma radiation is emitted by the source? ii. alpha and beta radiation might be emitted by the source? e) What further tests could you make using this arrangement to find out whether or not the source emits alpha radiation? National 5 Physics: Waves & Radiation 2 2. -
Uranium Fact Sheet
Fact Sheet Adopted: December 2018 Health Physics Society Specialists in Radiation Safety 1 Uranium What is uranium? Uranium is a naturally occurring metallic element that has been present in the Earth’s crust since formation of the planet. Like many other minerals, uranium was deposited on land by volcanic action, dissolved by rainfall, and in some places, carried into underground formations. In some cases, geochemical conditions resulted in its concentration into “ore bodies.” Uranium is a common element in Earth’s crust (soil, rock) and in seawater and groundwater. Uranium has 92 protons in its nucleus. The isotope2 238U has 146 neutrons, for a total atomic weight of approximately 238, making it the highest atomic weight of any naturally occurring element. It is not the most dense of elements, but its density is almost twice that of lead. Uranium is radioactive and in nature has three primary isotopes with different numbers of neutrons. Natural uranium, 238U, constitutes over 99% of the total mass or weight, with 0.72% 235U, and a very small amount of 234U. An unstable nucleus that emits some form of radiation is defined as radioactive. The emitted radiation is called radioactivity, which in this case is ionizing radiation—meaning it can interact with other atoms to create charged atoms known as ions. Uranium emits alpha particles, which are ejected from the nucleus of the unstable uranium atom. When an atom emits radiation such as alpha or beta particles or photons such as x rays or gamma rays, the material is said to be undergoing radioactive decay (also called radioactive transformation). -
Guide for the Use of the International System of Units (SI)
Guide for the Use of the International System of Units (SI) m kg s cd SI mol K A NIST Special Publication 811 2008 Edition Ambler Thompson and Barry N. Taylor NIST Special Publication 811 2008 Edition Guide for the Use of the International System of Units (SI) Ambler Thompson Technology Services and Barry N. Taylor Physics Laboratory National Institute of Standards and Technology Gaithersburg, MD 20899 (Supersedes NIST Special Publication 811, 1995 Edition, April 1995) March 2008 U.S. Department of Commerce Carlos M. Gutierrez, Secretary National Institute of Standards and Technology James M. Turner, Acting Director National Institute of Standards and Technology Special Publication 811, 2008 Edition (Supersedes NIST Special Publication 811, April 1995 Edition) Natl. Inst. Stand. Technol. Spec. Publ. 811, 2008 Ed., 85 pages (March 2008; 2nd printing November 2008) CODEN: NSPUE3 Note on 2nd printing: This 2nd printing dated November 2008 of NIST SP811 corrects a number of minor typographical errors present in the 1st printing dated March 2008. Guide for the Use of the International System of Units (SI) Preface The International System of Units, universally abbreviated SI (from the French Le Système International d’Unités), is the modern metric system of measurement. Long the dominant measurement system used in science, the SI is becoming the dominant measurement system used in international commerce. The Omnibus Trade and Competitiveness Act of August 1988 [Public Law (PL) 100-418] changed the name of the National Bureau of Standards (NBS) to the National Institute of Standards and Technology (NIST) and gave to NIST the added task of helping U.S. -
Copyright by Arthur Bryan Crawford 2004
Copyright by Arthur Bryan Crawford 2004 The Dissertation Committee for Arthur Bryan Crawford Certifies that this is the approved version of the following dissertation: Evaluation of the Impact of Non -Uniform Neutron Radiation Fields on the Do se Received by Glove Box Radiation Workers Committee: Steven Biegalski, Supervisor Sheldon Landsberger John Howell Ofodike Ezekoye Sukesh Aghara Evaluation of the Impact of Non -Uniform Neutron Radiation Fields on the Dose Received by Glove Box Radiation Workers by Arthur Bryan Crawford, B.S., M.S. Dissertation Presented to the Faculty of the Graduate School of The University of Texas at Austin in Partial Fulfillment of the Requirements for the Degree of Doctor of Philosophy The University of Texas at Austin December, 2004 Dedication I was born to goodly parents Harvey E. Crawford and Johnnie Lee Young Crawford Acknowledgements I would like to express my gratitude to Dr. Sheldon Landsberger for his vision in starting a distance learning program at the University of Texas at Austin and for his support and encouragement on this quest. I would like to thank my advisor, Dr. Steven Biegalski, for his support and encouragement even though the topic area was new to him. I would like to thank the members of my dissertation committee for finding the time to review this dissertation. To the staff of the Nuclear Engineering Teaching Laboratory I say thank you for your kindness and support during those brief times that I was on cam pus. A special thanks to my past and present group leaders, David Seidel, Eric McNamara, and Bill Eisele and my Division Leader, Lee McAtee, at Los Alamos National Laboratory, for their support in being allowed to use time and material resources at the Lab oratory and for financial support in the form of tuition reimbursement and travel expenses. -
Chapter 1, Section
Chapter 1 Chemical Foundations 1.3 Units of Measurement Copyright © 2005 by Pearson Education, Inc. Publishing as Benjamin Cummings 1 Measurement You make a measurement every time you • measure your height. • read your watch. • take your temperature. • weigh a cantaloupe. Copyright © 2005 by Pearson Education, Inc. Publishing as Benjamin Cummings 2 Measurement in Chemistry In chemistry we • measure quantities. • do experiments. • calculate results. • use numbers to report measurements. • compare results to standards. Copyright © 2005 by Pearson Education, Inc. Publishing as Benjamin Cummings 3 Measurement In a measurement • a measuring tool is used to compare some dimension of an object to a standard. • of the thickness of the skin fold at the waist, calipers are used. Copyright © 2005 by Pearson Education, Inc. Publishing as Benjamin Cummings 4 Stating a Measurement In every measurement, a number is followed by a unit. Observe the following examples of measurements: Number and Unit 35 m 0.25 L 225 lb 3.4 hr 5 The Metric System (SI) The metric system or SI (international system) is • a decimal system based on 10. • used in most of the world. • used everywhere by scientists. 6 The 7 Basic Fundamental SI Units Physical Quantity Name of Unit Abbreviation Mass kilogram kg Length meter m Time second s Temperature kelvin K Electric current ampere A Amount of substance mole mol Luminous intensity candela cd 7 Units in the Metric System In the metric and SI systems, one unit is used for each type of measurement: Measurement Metric SI Length meter (m) meter (m) Volume liter (L) cubic meter (m3) Mass gram (g) kilogram (kg) Time second (s) second (s) Temperature Celsius (°C) Kelvin (K) 8 Length Measurement Length • is measured using a meter stick. -
RAD 520-3 the Physics of Medical Dosimetry
RAD 520 The Physics of Medical Dosimetry I Fall Semester Syllabus COURSE DEFINITION: RAD 520-3 The Physics of Medical Dosimetry I- This course covers the following topics: Radiologic Physics, production of x-rays, radiation treatment and simulation machines, interactions of ionizing radiation, radiation measurements, dose calculations, computerized treatment planning, dose calculation algorithms, electron beam characteristics, and brachytherapy physics and procedures. This course is twenty weeks in length. Prerequisite: Admission to the Medical Dosimetry Program. COURSE OBJECTIVES: 1. Demonstrate an understanding of radiation physics for photons and electrons. 2. Demonstrate an understanding of the different types of radiation production. 3. Demonstrate an understanding of radiation dose calculations and algorithms. 4. Understand brachytherapy procedures and calculate radiation attenuation and decay. 5. Demonstrate an understanding of the different types of radiation detectors. 6. Demonstrate an understanding of general treatment planning. COURSE OUTLINE: Topics 1. Radiation physics 2. Radiation generators 3. External beam calculations 4. Brachytherapy calculations 5. Treatment planning 6. Electron beam physics COURSE REQUIREMENTS: Purchase all texts, attend all lectures, and complete required examinations, quizzes, and homeworks. Purchase a T130XA scientific calculator. PREREQUISITES: Admittance to the Medical Dosimetry Program. TEXTBOOKS: Required: 1. Khan, F. M. (2014). The physics of radiation therapy (5th ed.). Philadelphia: Wolters Kluwer 2. Khan, F.M. (2016). Treatment planning in radiation oncology (4th ed.). Philadelphia: Wolters Kluwer 3. Washington, C. M., & Leaver, D. T. (2015). Principles and practices of radiation therapy (4th Ed). St. Louis: Mosby. Optional: (Students typically use clinical sites’ copy) 1. Bentel, G. C. (1992). Radiation therapy planning (2nd ed.). New York: McGraw-Hill. -
Industrial Radiography
RADIATION PROTECTION OF WORKERS Industrial Radiography RADIATION AND RADIOGRAPHS RADIOACTIVE SOURCES PROCEDURES RADIOGRAPHERS DO follow the procedures. Ionizing radiation can pen- Materials of higher den Sealed sources are small þ Safe storage Precautions þ DO use the appropriate equipment, including collimators. in size and contain material etrate objects and create sity absorb more radiation. þ DO confi rm that there are no other people working in the images on photographic The metal components are which emits penetrating area of radiography. fi lm. The technique is revealed inside this tele radiation continuously. Radioactive sources should be kept in a secure, fi re þ DO use clear working signs and signals. called radiography and phone because they have Special containers made þ DO set up the controlled area and the necessary barriers. the processed fi lms are absorbed more radiation of dense metal shielding resistant and adequately shielded storage location þ DO confi rm the location of the source, or that X rays are called radiographs. than the surrounding plastic. are necessary to store, not being generated, by use of a survey meter. when not in use, and should move and manipulate these þ DO secure and store the source or X ray machine when sources. Due to their small be kept separate from other not in use. materials. The storage loca- size and manoeuvrability, Portable and mobile radiographic þ DO wear your personal dosimeter. sealed sources can be containers. ~ tion for X ray machines that used in confined spaces. are not in use is not required to be shielded. OTHER WORKERS Iridium-192 is a common radioactive source used þ DO observe the access restrictions, however remote it may in gamma radiography. -
Occupational Radiation Protection Record-Keeping and Reporting Guide
DOE G 441.1-11 (formerly G-10 CFR 835/H1) 05-20-99 OCCUPATIONAL RADIATION PROTECTION RECORD-KEEPING AND REPORTING GUIDE for use with Title 10, Code of Federal Regulations, Part 835, Occupational Radiation Protection Assistant Secretary for Environment, Safety and Health (THIS PAGE INTENTIONALLY LEFT BLANK) DOE G 441.1-11 i 05-20-99 CONTENTS CONTENTS PAGE 1. PURPOSE AND APPLICABILITY ........................................................ 1 2. DEFINITIONS ........................................................................ 2 3. DISCUSSION ........................................................................ 3 4. IMPLEMENTATION GUIDANCE ......................................................... 4 4.1 RECORDS TO BE GENERATED AND MAINTAINED ................................ 4 4.1.1 Individual Monitoring and Dose Records ........................................ 4 4.1.2 Monitoring and Workplace Records ............................................ 8 4.1.3 Administrative Records .................................................... 11 4.2 REPORTS ................................................................... 15 4.2.1 Reports to Individuals ...................................................... 16 4.2.2 Reports of Planned Special Exposures ......................................... 17 4.3 PRIVACY ACT CONSIDERATIONS .............................................. 17 4.3.1 Informing Individuals ...................................................... 17 4.3.2 Identifying Individuals ..................................................... 17 -
Development of Chemical Dosimeters Development Of
SUDANSUDAN ACADEMYAGADEMY OFOF SCIENCES(SAS)SGIENGES(SAS) ATOMICATOMIC ENERGYEhTERGYRESEARCHESRESEARCHES COORDINATIONCOORDII\rATI ON COUNCILCOUNCIL - Development of Chemical Dosimeters A dissertation Submitted in a partial Fulfillment of the Requirement forfbr Diploma Degree in Nuclear Science (Chemistry) By FareedFadl Alla MersaniMergani SupervisorDr K.S.Adam MurchMarch 2006 J - - - CONTENTS Subject Page -I - DedicationDedication........ ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... ... I Acknowledgement ... '" ... ... ... ... ... ... '" ... ... ... ... '" ... '" ....... .. 11II Abstract ... ... ... '" ... ... ... '" ... ... ... ... -..... ... ... ... ... ... ..... III -I Ch-lch-1 DosimetryDosimefry - 1-1t-l IntroductionLntroduction . 1I - 1-2t-2 Principle of Dosimetry '" '" . 2 1-3l-3 DosimetryDosimefiySystems . 3J 1-3-1l-3-l primary standard dosimeters '" . 4 - 1-3-2l-3-Z Reference standard dosimeters ... .. " . 4 1-3-3L-3-3 Transfer standard dosimeters ... ... '" . 4 1-3-4t-3-4 Routine dosimeters . 5 1-4I-4 Measurement of absorbed dose . 6 1-5l-5 Calibration of DosimetryDosimetrvsystemsvstem '" . 6 1-6l-6 Transit dose effects . 8 Ch-2ch-2 Requirements of chemical dosimeters 2-12-l Introduction ... ... ... .............................................. 111l 2-2 Developing of chemical dosimeters ... ... .. ....... ... .. ..... 12t2 2-3 Classification of Dosimetry methods.methods .......................... 14l4 2-4 RequirementsRequiremsnts of ideal chemical dosimeters ,. ... 15 2-5 Types of chemical system .