Radiation Safety
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Nuclear Threat
MANAGEMENT OF RADIOLOGIC CASUALTIES Nuclear Threat . Formerly .Soviet Union .Nuclear fallout . Now .NBC threat against civilians .Accidental exposure of workers and public Images: CIA, FBI Accidental Exposure in Brazil . Cesium-137 source found by scavengers in 1987 . Source broken open, contents shared . 112,800 surveyed for contamination . 120 externally contaminated only . 129 internally & externally contaminated . 20 required hospital treatment . 14 developed bone marrow depression . 8 treated with Granulocyte Macrophage Colony-Stimulating Factors (GM-CSF) . 4 died acute phase, hemorrhage, infection . 1 died in 1994 from liver failure Images: CIA Medical Staff Exposure Medical staff received doses: . Maximum 500 millirem (5 millisieverts) .Natural background radiation dose ~ 200 millirems annually . Average 20 millirem (0.2 millisieverts) .Equivalent to one chest X-ray Juarez, Mexico Incident . 400 curies of cobalt-60 in stainless steel therapy device sold for scrap . Ended up in recycled steel rebar . Wrong turn into Los Alamos lab . I0 people significantly exposed . 1 construction worker died .bone cancer . 109 houses demolished in Mexico Images: CIA US Experience 1944-1999 . 243 radiation accidents leading to “serious” classification . 790 people received significant exposure resulting in 30 fatalities .Incidents included: . 137 industrial . 80 medical . 11 criticality Image: DOE The Basics of Radiation Radiation is energy that comes from a source and travels through matter or space Radioactivity is the spontaneous emission of radiation: . Either directly from unstable atomic nuclei, or . As a consequence of a nuclear reaction, or . Machine – produced (X-ray) Image: NOAA Contamination . Defined as internal or external deposition of radioactive particles . Irradiation continues until source removed by washing, flushing or radioactive decay . -
The Utilization of MOSFET Dosimeters for Clinical Measurements in Radiology
The Utilization of MOSFET Dosimeters for Clinical Measurements in Radiology David Hintenlang, Ph.D., DABR, FACMP Medical Physics Program Director J. Crayton Pruitt Family Department of Biomedical Engineering J. Crayton Pruitt Family Department of Biomedical Engineering Medical Physics Program Conflict of interest statement: The presenter holds no financial interest in, and has no affiliation or research support from any manufacturer or distributor of MOSFET Dosimetry systems. J. Crayton Pruitt Family Department of Biomedical Engineering Medical Physics Program The MOSFET Dosimeter • Metal oxide silicon field effect transistor • Uniquely packaged to serve as a radiation detector – developed as early as 1974 • Applications – Radiation Therapy Dose Verification – Cosmic dose monitoring on satellites – Radiology • ~ 1998 - present J. Crayton Pruitt Family Department of Biomedical Engineering Medical Physics Program Attractive features • Purely electronic dosimeter • Provides immediate dose feedback • Integrates over short periods of time • Small size and portability • Simultaneous measurements (up to 20) J. Crayton Pruitt Family Department of Biomedical Engineering Medical Physics Program Demonstrated radiology applications – Patient dose monitoring/evaluation • Radiography • Fluoroscopic and interventional procedures • CT • Mammography J. Crayton Pruitt Family Department of Biomedical Engineering Medical Physics Program Principles of operation • Ionizing radiation results in the creation of electron-hole pairs • Holes migrate and build up -
Radiation Survey Meters in Hospitals: Technology, Challenges, and a New Approach
White paper Radiation survey meters in hospitals: technology, challenges, and a new approach This white paper introduces a new radiation sur- essary environmental radiation in hospitals. To vey meter for the hospital segment: the RaySafe lower the risks of unwanted radiation-induced 452. First, the need for survey meters in hospi- effects, the goal is to minimize the exposure to tal environments is described. This is followed unnecessary radiation, both for patients and staff. by an introduction to common survey meter To be able to take the correct measures, it is es- technologies to illustrate their possibilities and sential to know the properties of the radiation in delimitations. Next, some difficulties with survey terms of energy range, dose rate, type of radia- meter measurements in hospitals are identified tion, and more. This is where radiation survey and discussed. Finally, the technology inside the meters are needed. RaySafe 452 is presented to summarize how the instrument addresses the identified issues. Figure 1 illustrates some measurement scenarios and demonstrate the wide range of measurement 1. Why radiation survey meters are need- needs in hospitals. Table 1 gives an overview of ed in hospitals the main areas of application of survey meters in hospitals, with quantities, units, and typical Ionizing radiation is not visible to the human eye. energy ranges of the radiation. It does not smell or make a noise, and you cannot feel it. In the complex and busy environment of a hospital, how can you ensure that patients and staff are not exposed to more ionizing radiation than necessary? Ionizing radiation is utilized for different purposes in medical procedures, with the three main areas being diagnostic imaging, nuclear medicine, and radiotherapy. -
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. -
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 -
Experiment "Gamma Dosimetry and Dose Rate Determination" Instruction for Experiment "Gamma Dosimetry and Dose Rate Determination"
TECHNICAL UNIVERSITY DRESDEN Institute of Power Engineering Training Reactor Reactor Training Course Experiment "Gamma Dosimetry and Dose Rate Determination" Instruction for Experiment "Gamma Dosimetry and Dose Rate Determination" Content: 1 .... Motivation 2..... Theoretical Background 2.1... Properties of Ionising Radiation and Interactions of Gamma Radiation 2.2. Detection of Ionising Radiation 2.3. Quantities and Units of Dosimetry 3..... Procedure of the Experiment 3.1. Commissioning and Calibration of the Dosimeter Thermo FH40G 3.2. Commissioning and Calibration of the Dosimeter Berthold LB 133-1 3.3. Commissioning and Calibration of the Dosimeter STEP RGD 27091 3.4. Setup of the Experiment 3.4.1. Measurement of Dose Rate in Various Distances from the Radiation Source 3.4.2. Measurement of Dose Rate behind Radiation Shielding 3.5. Measurement of Dose Rate at the open Reactor Channel 4..... Evaluation of Measuring Results Figures: Fig. 1: Composition of the attenuation coefficient µ of γ-radiation in lead Fig. 2: Design of an ionisation chamber Fig. 3: Classification and legal limit values of radiation protection areas Fig. 4: Setup of the experiment (issued: January 2019) - 1 - 1. Motivation The experiment aims on familiarising with the methods of calibrating different detectors for determination of the dose and the dose rate. Furthermore, the dose rate and the activity in the vicinity of an enclosed source of ionising radiation (Cs-137) will be determined taking into account the background radiation and the measurement accuracy. Additionally, the experiment focuses on the determination of the dose rate of a shielded source as well as on the calculation of the required thickness of the shielding protection layer for meeting the permissible maximum dose rate. -
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 . -
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).