Radiation Safety Initial Training
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CNS Ionising Radiation Workshop Notes
Ionising Radiation Workshop Page 1 of 82 Canadian Nuclear Society Ionising Radiation Workshop Be Aware of NORM CNS Team Bryan White Doug De La Matter Peter Lang Jeremy Whitlock First presented concurrently at: The Science Teachers’ Association of Ontario Annual Conference, Toronto; and The Alberta Teachers’ Association Science Council Conference, Calgary 2008 November 14 Revision 12 Presentation at: Association of Science Teachers Provincial Conference 2013 Halifax NS October 25th, 2013 Ionising Radiation Workshop Page 2 of 82 Revision History Revision 1: 2008-11-06 (Note revisions modify page numbers) Page Errata 10 Last paragraph: “…emit particles containing (only) two protons …” (add parentheses) 11 Table, Atomic No. 86, 1st radon mass number should be 220. 20 Insert section 3.4 Shielding – affects page numbers 24 1st paragraph: “…with the use of shielding absorbers.” (insert “shielding”) 26 1st paragraph: “… of consistent data can be time consuming.” (delete “it”) 32 List item 6, last sentence: “The container contents have an activity of about 5 kBq.” (emphasis on contents) 44 2nd paragraph, 4th sentence: “… surface exposure of 360 µSv to 8.8 mSv …” (µSv not mSv) 45 2nd paragraph, 2nd sentence: “ … radioactivity compared to thorium ore …” (delete “the”) 47 2nd paragraph: “Because the lens diameter is not much smaller …” (insert “not”) Revision 2: 2009-02-04 5 Deleted 2 pages re CNA website S 3.2 Discussion of radon decay and health hazard inserted 38 Experiment 3, Part I – results from a more extensive absorber experiment show that the alpha radiation scatters electrons from the foils with energy higher than the beta from the thorium decay chain 51 Appendix C (now D): Note added that more recent “non-divide-by-two” modules are also red in colour. -
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 -
AFRRI Biodosimetry Worksheet
Armed Forces Radiobiology Research Institute Biodosimetry Worksheet (Medical Record of Radiation Dose, Contamination, and Acute Radiation Sickness Response) Reporting Authority (person(s) creating this page of the report) Last name: First name: Country of origin: Unit: Phone: Fax: Email: Location: Date (yymmdd): Time: Casualty Last name: First name: Rank: Country of origin: Parent unit: Parent unit location: Parent unit phone: Unit e-mail: Unit fax: Casualty location: History of presenting injury (conventional and/or radiation): History of previous radiation exposure: Past medical history (general): Medical countermeasures (e.g., antiemetics, transfusion), specify: Administered (where, when, route): Exposure conditions Date of exposure (yymmdd): Exposure location: Time of exposure: Weather conditions (at time of exposure): Exposure results Describe incident: External exposure overview Contamination overview Body exposure: Total Partial Uncertain External contamination: Yes No Shielding confounder: Yes No Internal contamination: Yes No Contaminated wound: Yes No If wound(s) are radiation contaminated, please provide details here: Biodosimetric assays overview Sampling date, time Estimated time Dose Reference radiation quality yymmdd (time) post-exposure (h) (Gy) and dose rate (Gy/min) Time onset of vomiting: Lymphocyte counts or depletion kinetics: Urine bioassay: Cytogenetic biodosimetry: Other: ARS response category overview (maximum grading 0-4; see pages 4 through 6 for guidance) N: C: G: H: = RC: days after radiation exposure: AFRRI -
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). -
Appendix B: Recommended Procedures
Recommended Procedures Appendix B Appendix B: Recommended Procedures Appendix B provides recommended procedures for tasks frequently performed in the laboratory. These procedures outline acceptable methods for meeting radiation safety requirements. The procedures are generic in nature, allowing for the diversity of research facilities, on campus. Contamination Survey Procedures Surveys are performed to monitor for the presence of contamination. Minimum survey frequencies are specified on the radiation permit. The surveys should be sufficiently extensive to allow confidence that there is no contamination. Common places to check for contamination are: bench tops, tools and equipment, floors, telephones, floors, door handles and drawer pulls, and computer keyboards. Types of Contamination Removable contamination can be readily transferred from one surface to another. Removable contamination may present an internal and external hazard because it can be picked up on the skin and ingested. Fixed contamination cannot be readily removed and generally does not present a significant hazard unless the material comes loose or is present large enough amounts to be an external hazard. Types of Surveys There are two types of survey methods used: 1) a direct (or meter) survey, and 2) a wipe (or smear) survey. Direct surveys, using a Geiger-Mueller (GM) detector or scintillation probe, can identify gross contamination (total contamination consisting of both fixed and removable contamination) but will detect only certain isotopes. Wipe surveys, using “wipes” such as cotton swabs or filter papers counted on a liquid scintillation counter or gamma counter can identify removable contamination only but will detect most isotopes used at the U of I. Wipe surveys are the most versatile and sensitive method of detecting low-level removable contamination in the laboratory. -
Digital Radiation Monitor Is a Health and Safety Instrument That Measures Alpha, Digital Radiation Monitor Beta, and Gamma Radiation
1 Introduction The Digital Radiation Monitor is a health and safety instrument that measures alpha, Digital Radiation Monitor beta, and gamma radiation. With the Digital Radiation Monitor, you can: • Monitor possible radiation exposure while working near radionuclides (Order Code DRM-BTD) • Ensure compliance with regulatory standards Contents • Check for leakage from X-ray machines and other sources • Screen for environmental contamination or environmental sources of 1 Introduction ............................................................................................................. 2 radioactivity How the DRM Detects Radiation ................................................................. 2 • Connect the Digital Radiation Monitor to a computer or data logger to record 2 Features ................................................................................................................... 3 and tabulate your data The Display................................................................................................... 3 The Switches ................................................................................................4 This manual gives complete instructions for using the Digital Radiation Monitor and The Detector..................................................................................................5 procedures for common applications. The Ports....................................................................................................... 5 3 Operation................................................................................................................ -
Radiation Basics
Environmental Impact Statement for Remediation of Area IV \'- f Susana Field Laboratory .A . &at is radiation? Ra - -.. - -. - - . known as ionizing radiatios bScause it can produce charged.. particles (ions)..- in matter. .-- . 'I" . .. .. .. .- . - .- . -- . .-- - .. What is radioactivity? Radioactivity is produced by the process of radioactive atmi trying to become stable. Radiation is emitted in the process. In the United State! Radioactive radioactivity is measured in units of curies. Smaller fractions of the curie are the millicurie (111,000 curie), the microcurie (111,000,000 curie), and the picocurie (1/1,000,000 microcurie). Particle What is radioactive material? Radioactive material is any material containing unstable atoms that emit radiation. What are the four basic types of ionizing radiation? Aluminum Leadl Paper foil Concrete Adphaparticles-Alpha particles consist of two protons and two neutrons. They can travel only a few centimeters in air and can be stopped easily by a sheet of paper or by the skin's surface. Betaparticles-Beta articles are smaller and lighter than alpha particles and have the mass of a single electron. A high-energy beta particle can travel a few meters in the air. Beta particles can pass through a sheet of paper, but may be stopped by a thin sheet of aluminum foil or glass. Gamma rays-Gamma rays (and x-rays), unlike alpha or beta particles, are waves of pure energy. Gamma radiation is very penetrating and can travel several hundred feet in air. Gamma radiation requires a thick wall of concrete, lead, or steel to stop it. Neutrons-A neutron is an atomic particle that has about one-quarter the weight of an alpha particle. -
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. -
The International Commission on Radiological Protection: Historical Overview
Topical report The International Commission on Radiological Protection: Historical overview The ICRP is revising its basic recommendations by Dr H. Smith Within a few weeks of Roentgen's discovery of gamma rays; 1.5 roentgen per working week for radia- X-rays, the potential of the technique for diagnosing tion, affecting only superficial tissues; and 0.03 roentgen fractures became apparent, but acute adverse effects per working week for neutrons. (such as hair loss, erythema, and dermatitis) made hospital personnel aware of the need to avoid over- Recommendations in the 1950s exposure. Similar undesirable acute effects were By then, it was accepted that the roentgen was reported shortly after the discovery of radium and its inappropriate as a measure of exposure. In 1953, the medical applications. Notwithstanding these observa- ICRU recommended that limits of exposure should be tions, protection of staff exposed to X-rays and gamma based on consideration of the energy absorbed in tissues rays from radium was poorly co-ordinated. and introduced the rad (radiation absorbed dose) as a The British X-ray and Radium Protection Committee unit of absorbed dose (that is, energy imparted by radia- and the American Roentgen Ray Society proposed tion to a unit mass of tissue). In 1954, the ICRP general radiation protection recommendations in the introduced the rem (roentgen equivalent man) as a unit early 1920s. In 1925, at the First International Congress of absorbed dose weighted for the way different types of of Radiology, the need for quantifying exposure was radiation distribute energy in tissue (called the dose recognized. As a result, in 1928 the roentgen was equivalent in 1966). -
Radiation Safety in Fluoroscopy
Radiation Safety for New Medical Physics Graduate Students John Vetter, PhD Medical Physics Department UW School of Medicine & Public Health Background and Purpose of This Training . This is intended as a brief introduction to radiation safety from the perspective of a Medical Physicist. Have a healthy respect for radiation without an undue fear of it. The learning objectives are: . To point out the sources of ionizing radiation in everyday life and at work. To present an overview of the health effects of ionizing radiation. To show basic concepts and techniques used to protect against exposure to ionizing radiation. Further training in Radiation Safety can be found at: https://ehs.wisc.edu/radiation-safety-training/ Outline . Ionizing Radiation . Definition, Quantities & Units . Levels of Radiation Exposure . Background & Medical . Health Effects of Radiation Exposure . Stochastic & Deterministic . Limits on Radiation Exposure . Rationale for Exposure Limits . Minimizing Radiation Exposure . Time, Distance, Shielding, Containment Definition of Ionizing Radiation . Radiation can be thought of as energy in motion. Electromagnetic radiation is pure energy that moves at the speed of light in the form of photons and includes: radio waves; microwaves; infrared, visible and ultraviolet light; x-rays and γ-rays. A key difference between these forms of electromagnetic radiation is the amount of energy that each photon carries. Some ultraviolet light, and X-rays and Gamma-rays have enough energy to remove electrons from atoms as they are absorbed, forming positive and negatively charged ions. These forms of radiation are called ionizing radiation. Radio waves, microwaves, infrared and visible light do not have enough energy to ionize atoms. -
Laboratoire National Henri Becquerel Ccri(I)/01-05 Dimri/Lnhb/Bc/01-146 30/03/01
BUREAU NATIONAL DE MÉTROLOGIE COMMISSARIAT À L'ÉNERGIE ATOMIQUE LABORATOIRE NATIONAL HENRI BECQUEREL CCRI(I)/01-05 DIMRI/LNHB/BC/01-146 30/03/01 BUREAU NATIONAL DE METROLOGIE Laboratoire National Henri Becqurel (BNM-LNHB) Laboratoire Central des Industries Electriques (BNM-LCIE) DOSIMETRY OF PHOTONS AND CHARGED PARTICLES Progress Report 2000-2001 B.Chauvenet Participation in the CCRI K4 key comparison on calibration factors of ionisation chambers in terms of absorbed dose to water for 60Co photons Comparison of standards of absorbed dose to water for high-energy photon beams with METAS A comparison was carried out with METAS in October 2000. This comparison dealt with air kerma and absorbed dose to water standards in 60Co beams, and absorbed dose to water standards for high-energy x rays from accelerators (6 MV, 12 MV and 20 MV). The comparison was carried out in BNM-LNHB beams (60Co and Saturne 43 accelerator), with transfer chambers from METAS. Results are under analysis. Comparison of standards of absorbed dose to water for high-energy photon beams with NRC This comparison was carried out in October 1998. The results were discussed and analysed, and will be presented in a paper which has been submitted to “Physics in Medicine and Biology”. EUROMET projects Participation in EUROMET Contact Persons meetings for the preparation of CMC tables. The laboratory will participate in the proposed project of METAS on quality factors for high-energy photon beams. Absorbed dose to graphite by calorimetry The realisation of a new graphite calorimeter is under study to replace the present one built in 1984.