Fundamental Principles of Radiation
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Glossary Derived From: Human Research Program Integrated Research Plan, Revision A, (January 2009)
Glossary derived from: Human Research Program Integrated Research Plan, Revision A, (January 2009). National Aeronautics and Space Administration, Johnson Space Center, Houston, Texas 77058, pages 232-280. Report No. 153: Information Needed to Make Radiation Protection Recommendations for Space Missions Beyond Low-Earth Orbit (2006). National Council on Radiation Protection and Measurements, pages 309-318. Reprinted with permission of the National Council on Radiation Protection and Measurements, http://NCRPonline.org . Managing Space Radiation Risk in the New Era of Space Exploration (2008). Committee on the Evaluation of Radiation Shielding for Space Exploration, National Research Council. National Academies Press, pages 111-118. -A- AAPM: American Association of Physicists in Medicine. absolute risk: Expression of excess risk due to exposure as the arithmetic difference between the risk among those exposed and that obtaining in the absence of exposure. absorbed dose (D): Average amount of energy imparted by ionizing particles to a unit mass of irradiated material in a volume sufficiently small to disregard variations in the radiation field but sufficiently large to average over statistical fluctuations in energy deposition, and where energy imparted is the difference between energy entering the volume and energy leaving the volume. The same dose has different consequences depending on the type of radiation delivered. Unit: gray (Gy), equivalent to 1 J/kg. ACE: Advanced Composition Explorer Mission, launched in 1997 and orbiting the L1 libration point to sample energetic particles arriving from the Sun and interstellar and galactic sources. It also provides continuous coverage of solar wind parameters and solar energetic particle intensities (space weather). When reporting space weather, it can provide an advance warning (about one hour) of geomagnetic storms that can overload power grids, disrupt communications on Earth, and present a hazard to astronauts. -
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 -
Basics of Radiation Radiation Safety Orientation Open Source Booklet 1 (June 1, 2018)
Basics of Radiation Radiation Safety Orientation Open Source Booklet 1 (June 1, 2018) Before working with radioactive material, it is helpful to recall… Radiation is energy released from a source. • Light is a familiar example of energy traveling some distance from its source. We understand that a light bulb can remain in one place and the light can move toward us to be detected by our eyes. • The Electromagnetic Spectrum is the entire range of wavelengths or frequencies of electromagnetic radiation extending from gamma rays to the longest radio waves and includes visible light. Radioactive materials release energy with enough power to cause ionizations and are on the high end of the electromagnetic spectrum. • Although our bodies cannot sense ionizing radiation, it is helpful to think ionizing radiation behaves similarly to light. o Travels in straight lines with decreasing intensity farther away from the source o May be reflected off certain surfaces (but not all) o Absorbed when interacting with materials You will be using radioactive material that releases energy in the form of ionizing radiation. Knowing about the basics of radiation will help you understand how to work safely with radioactive material. What is “ionizing radiation”? • Ionizing radiation is energy with enough power to remove tightly bound electrons from the orbit of an atom, causing the atom to become charged or ionized. • The charged atoms can damage the internal structures of living cells. The material near the charged atom absorbs the energy causing chemical bonds to break. Are all radioactive materials the same? No, not all radioactive materials are the same. -
Cherenkov Radiation
TheThe CherenkovCherenkov effecteffect A charged particle traveling in a dielectric medium with n>1 radiates Cherenkov radiation B Wave front if its velocity is larger than the C phase velocity of light v>c/n or > 1/n (threshold) A β Charged particle The emission is due to an asymmetric polarization of the medium in front and at the rear of the particle, giving rise to a varying electric dipole momentum. dN Some of the particle energy is convertedγ = 491into light. A coherent wave front is dx generated moving at velocity v at an angle Θc If the media is transparent the Cherenkov light can be detected. If the particle is ultra-relativistic β~1 Θc = const and has max value c t AB n 1 cosθc = = = In water Θc = 43˚, in ice 41AC˚ βct βn 37 TheThe CherenkovCherenkov effecteffect The intensity of the Cherenkov radiation (number of photons per unit length of particle path and per unit of wave length) 2 2 2 2 2 Number of photons/L and radiation d N 4π z e 1 2πz 2 = 2 1 − 2 2 = 2 α sin ΘC Wavelength depends on charge dxdλ hcλ n β λ and velocity of particle 2πe2 α = Since the intensity is proportional to hc 1/λ2 short wavelengths dominate dN Using light detectors (photomultipliers)γ = sensitive491 in 400-700 nm for an ideally 100% efficient detector in the visibledx € 2 dNγ λ2 d Nγ 2 2 λ2 dλ 2 2 11 1 22 2 d 2 z sin 2 z sin 490393 zz sinsinΘc photons / cm = ∫ λ = π α ΘC ∫ 2 = π α ΘC 2 −− 2 = α ΘC λ1 λ1 dx dxdλ λ λλ1 λ2 d 2 N d 2 N dλ λ2 d 2 N = = dxdE dxdλ dE 2πhc dxdλ Energy loss is about 104 less hc 2πhc than 2 MeV/cm in water from € -
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. -
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 . -
Measuring Radioactivity
Health Physics Society Public Education Committee Fact Sheet MEASURING RADIOACTIVITY Because ionizing radiation cannot be detected with our human senses, we use various types of instruments and radiation detectors to measure the amount of radiation present. We usually measure both the amount of radioactivity in a radioisotope source, and the ionizing radiation field density being emitted by the source. We define radioactivity as the number of atoms which decay (disintegrate) in a radioisotope sample in a given period of time. The base unit is the Becquerel (Bq) or one disintegration per second (dps). This number is very small and therefore, not very useful. For this reason we use the Curie (Ci) which is 37 billion Bq. Because we often use very large or very small numbers when discussing radioactivity, we use a series o f prefixes which express multiples of 1000. The following table shows some of these prefixes: milli (m) = 1/1,000 kilo (k) = times 1,000 micro (u) = 1/1,000,000 mega (M) = times 1,000,000 nano (n) 1/1,000,000,000 giga (G) times 1,000,000,000 Pico (P) 1/1,000,000,000,000 tera (T) times 1,000,000,000,000 Using the table, a mCi = 1/1000 of a Curie and a GBq 1,000,000,000 Becquerels. To put this in perspective, a normal home smoke detector contains a small sealed source of about 10 uCi (370,000 Bq) of radioactivity. Ionizing radiation fields are expressed in units of Roentgens (R) which is equivalent to the number of atoms of a gas which are ionized.