Radiation Protection Training Manual & Study Guide
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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 -
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 Glossary
Radiation Glossary Activity The rate of disintegration (transformation) or decay of radioactive material. The units of activity are Curie (Ci) and the Becquerel (Bq). Agreement State Any state with which the U.S. Nuclear Regulatory Commission has entered into an effective agreement under subsection 274b. of the Atomic Energy Act of 1954, as amended. Under the agreement, the state regulates the use of by-product, source, and small quantities of special nuclear material within said state. Airborne Radioactive Material Radioactive material dispersed in the air in the form of dusts, fumes, particulates, mists, vapors, or gases. ALARA Acronym for "As Low As Reasonably Achievable". Making every reasonable effort to maintain exposures to ionizing radiation as far below the dose limits as practical, consistent with the purpose for which the licensed activity is undertaken. It takes into account the state of technology, the economics of improvements in relation to state of technology, the economics of improvements in relation to benefits to the public health and safety, societal and socioeconomic considerations, and in relation to utilization of radioactive materials and licensed materials in the public interest. Alpha Particle A positively charged particle ejected spontaneously from the nuclei of some radioactive elements. It is identical to a helium nucleus, with a mass number of 4 and a charge of +2. Annual Limit on Intake (ALI) Annual intake of a given radionuclide by "Reference Man" which would result in either a committed effective dose equivalent of 5 rems or a committed dose equivalent of 50 rems to an organ or tissue. Attenuation The process by which radiation is reduced in intensity when passing through some material. -
THESIS VERIFICATION of BACKGROUND REDUCTION in a LIQUID SCINTILLATION COUNTER Submitted by Marilyn Alice Magenis Department of E
THESIS VERIFICATION OF BACKGROUND REDUCTION IN A LIQUID SCINTILLATION COUNTER Submitted by Marilyn Alice Magenis Department of Environmental and Radiological Health Sciences In partial fulfillment of the requirements For the Degree of Master of Science Colorado State University Fort Collins, Colorado Summer 2013 Master’s Committee: Advisor: Alexander Brandl Thomas E. Johnson John Volckens John Harton ABSTRACT VERIFICATION OF BACKGROUND REDUCTION IN A LIQUID SCINTILLATION COUNTER A new method for subtraction of extraneous cosmic ray background counts from liquid scintillation detection has been developed by HidexTM. The method uses a background counter located beneath the liquid scintillation detector, the guard, to account for background signals. A double to triple coincidence counting methodology is used to reduce photomultiplier noise and to quantify quench. It is important to characterize the interactions from background in any new system. Characterizing interactions in the instrument will help to verify the accuracy and efficiency of the guard by determining the noise cancellation capabilities of the liquid scintillation counter. The liquid scintillation counter and guard detector responses were modeled using MCNP for the expected cosmic ray interactions at the instrument location and altitude in Fort Collins, CO. Cosmic ray interactions in the detector are most relevant to examine because of their predominance due to the higher elevation in Fort Collins. The cosmic ray interactions that are most important come from electron, positron, and gamma interactions. The expected cosmic ray interactions from these particles were modeled by using a cosmic ray library that determines the cosmic rays that are most likely to occur at an altitude of 2100 meters. -
Ranger Operating Manual
INTERNATIONAL ® S.E. International, Inc. P.O. Box 39, 436 Farm Rd. Summertown, TN 38483 USA 1.800.293.5759 | 931.964.3561 | Fax: 1.931.964.3564 www.seintl.com | [email protected] Contents Chapter 1: Introduction 3 Preferences 14 How The unit Detects Radiation 3 Using the Data Logging Feature 14 Precautions 3 Show Grid 15 Observer USB Chart Screen 15 Chapter 2: Features 4 The X Axis 15 The LCD Display 4 The Y Axis 15 Indicators 4 Observer USB Meter Screen 15 The Buttons 5 Enable Alarm 15 Power Button 5 Zero 15 Alarm Button 5 Units/Echo Display 15 Count Button 5 Cal Panel (Calibration Panel) 16 Audio Button 5 Calibration Information 16 Menu Button 5 Applied Isotope 16 Backlight Button 5 Alarm Settings 16 Mode Button 6 Preset Counting Time (min) 16 The Detector 6 Data Logging Settings 16 USB Jack 6 Backlight On Time 16 Lanyard 6 Auto-Averaging 16 Xtreme Boot 6 Audio Settings 16 Chapter 3: Operation 7 Starting The unit 7 Chapter 8: Built in Isotope Efficiencies 17 Units of Measurement 7 Built in Isotope Efficiencies 17 Display Update 7 Decay 17 Maximum level 7 Selecting a Built-In Isotope Efficiency 17 Response Time (Autoaveraging) 7 Adding A Custom Isotope Efficiency 17 Autoranging 8 Operating in Dose/Rate Modes 8 Chapter 9: Observer USB Calibration Software 18 Using The Alarm 8 General Discussion of Calibration 18 Operating in Count Mode 9 Pulse Based Pre-Calibration 18 How To Take A Timed Count 9 Efficiency Calibration 19 Using Dose/Rate Modes While Timer is On 9 Exposure Rate Calibration 20 The Menu 10 Menu Options 10 Chapter 10: Troubleshooting 22 Setting the Internal Clock 10 Interfacing with an External Device 10 Chapter 11: Basics of Taking Measurements 23 How to Detect Background Radiation 23 Chapter 4: Common Procedures 11 How To Survey a Surface 23 Establishing the Background Count 11 How to Perform a General Survey 23 Environmental Area Monitoring 11 How to Determine Alpha, Beta, or Gamma source. -
Liquid Scintillation Counting
Institutionen för medicin och vård Avdelningen för radiofysik Hälsouniversitetet Liquid Scintillation Counting Sten Carlsson Department of Medicine and Care Radio Physics Faculty of Health Sciences Series: Report / Institutionen för radiologi, Universitetet i Linköping; 78 ISSN: 1102-1799 ISRN: LIU-RAD-R-078 Publishing year: 1993 © The Author(s) Report 78 lSSN 1102-1799 Nov 1993 lSRN ULI-RAD-R--78--SE Liquid Scintillation Counting Sten Carlsson Dept of Radiation Physlcs Dept Medical Physlcs Linköping Unlverslly , Sweden: UddevalIa,Svveden i 1. INTRODUCTIQN In liquid scintillation counting (LSC) we use the process ofluminescense to detect ionising radiation emit$ed from a radionuclide. Luminescense is emission of visible light ofnon thermal origin. 1t was early found that certain organic molecules have luminescent properties and such molecules are used in LSC. Today LSC is the mostwidespread method to detect pure beta-ernitters like tritium and carbon-14. 1t has unique properties in its efficient counting geometry, deteetability and the lack of any window which the beta particles have to penetrate. These properties are achieved by solving the sample to measure in a scintillation cocktail composed of an organic solvent and a solute (scintillator). Even if LSC is a weil established measurement technique, the user can run into problems and abasic knowledge of the deteetor and its different components is offundamental importance in a correct use of the technique. The alm of this presentation is to provide the user with some of this fundamental knowledge. 2. BAS1C PRINCIPLE LSC is based on the principle oftransformlng some of the kinetic energy of the beta-partic1e into light photons. -
Radiation Safety Guide Research Use of Radioactive Materials
Radiation Safety Guide Research Use of Radioactive Materials Table of Contents Page RADIATION AND RADIOACTIVITY 4 A. Decay by Alpha (α)-Particle Emission 4 B. Decay by Beta (β)− Particle Emission 5 C. Decay by Gamma Ray (γ) emission 5 D. Decay by Electron Capture (X-ray) 5 E. Other sources of Radiation 5 F. Neutron particles (n) 6 G. Radiation Quantities 6 H. Half-life, Biological half-life, Effective half-life 7 I. Radiation Detection Instrument 8 1. Gas-filled detectors 8 2. Scintillation Detector 8 J. Background Radiation 9 K. Biological Effect of Radiation 10 PRINCIPLES OF RADIATION SAFETY 11 A. Occupational Dose Limit 11 B. Public Dose 11 D. Dose to an Embryo/Fetus 11 E. Registration of Radiation Workers 12 F. Personnel Monitoring 12 G. Type of Dosimeters 12 H. Dosimeter Placement 12 I. Internal Monitoring 13 J. Exposure Reports 13 K. ALARA 13 L.Posting 14 1 RADIATION SAFETY PROGRAM 16 A. Individuals Responsible For Radiation Safety Program 16 B. Organization Chart 16 C. Radiation Safety Committee 16 D. Radiation Safety Officer 17 E. Authorized Users 18 F. Radiation Workers 19 G. Radioactive Drug Research Committee (RDRC) 19 H. Medical Radiation Subcommittee (MRC) 22 RADIATION SAFETY PROCEDURES 23 A. Training Program 23 1. Initial Radiation Safety Training 24 2. Annual Refresher Training 24 3. Radiation Safety Training for Clinical Staff 24 4. Radiation Safety Training for House Keeping, Physical Plant and Security Staff 24 5. Radiation Safety Training for irradiator workers 24 B. Audit Program 24 C. Survey Program 25 1. Survey for Removable Contamination 27 2. -
Lumi-Scint Liquid Scintillation Counter
DOE/EM-0596 Lumi-Scint Liquid Scintillation Counter Deactivation and Decommissioning Focus Area Prepared for U.S. Department of Energy Office of Environmental Management Office of Science and Technology July 2001 Lumi-Scint Liquid Scintillation Counter OST/TMS ID 2311 Deactivation and Decommissioning Focus Area Demonstrated at Miamisburg Environmental Management Project Miamisburg, Ohio Purpose of this document Innovative Technology Summary Reports are designed to provide potential users with the information they need to quickly determine if a technology would apply to a particular environmental management problem. They are also designed for readers who may recommend that a technology be considered by prospective users. Each report describes a technology, system, or process that has been developed and tested with funding from DOE’s Office of Science and Technology (OST). A report presents the full range of problems that a technology, system, or process will address and its advantages to the DOE cleanup in terms of system performance, cost, and cleanup effectiveness. Most reports include comparisons to baseline technologies as well as other competing technologies. Information about commercial availability and technology readiness for implementation is also included. Innovative Technology Summary Reports are intended to provide summary information. References for more detailed information are provided in an appendix. Efforts have been made to provide key data describing the performance, cost, and regulatory acceptance of the technology. If this information was not available at the time of publication, the omission is noted. All published Innovative Technology Summary Reports are available on the OST website at www.em.doe.gov/ost under “Publications.” TABLE OF CONTENTS 1. -
Radiation Safety
RADIATION SAFETY FOR LABORATORY WORKERS RADIATION SAFETY PROGRAM DEPARTMENT OF ENVIRONMENTAL HEALTH, SAFETY AND RISK MANAGEMENT UNIVERSITY OF WISCONSIN-MILWAUKEE P.O. BOX 413 LAPHAM HALL, ROOM B10 MILWAUKEE, WISCONSIN 53201 (414) 229-4275 SEPTEMBER 1997 (REVISED FROM JANUARY 1995 EDITION) CHAPTER 1 RADIATION AND RADIOISOTOPES Radiation is simply the movement of energy through space or another media in the form of waves, particles, or rays. Radioactivity is the name given to the natural breakup of atoms which spontaneously emit particles or gamma/X energies following unstable atomic configuration of the nucleus, electron capture or spontaneous fission. ATOMIC STRUCTURE The universe is filled with matter composed of elements and compounds. Elements are substances that cannot be broken down into simpler substances by ordinary chemical processes (e.g., oxygen) while compounds consist of two or more elements chemically linked in definite proportions. Water, a compound, consists of two hydrogen and one oxygen atom as shown in its formula H2O. While it may appear that the atom is the basic building block of nature, the atom itself is composed of three smaller, more fundamental particles called protons, neutrons and electrons. The proton (p) is a positively charged particle with a magnitude one charge unit (1.602 x 10-19 coulomb) and a mass of approximately one atomic mass unit (1 amu = 1.66x10-24 gram). The electron (e-) is a negatively charged particle and has the same magnitude charge (1.602 x 10-19 coulomb) as the proton. The electron has a negligible mass of only 1/1840 atomic mass units. The neutron, (n) is an uncharged particle that is often thought of as a combination of a proton and an electron because it is electrically neutral and has a mass of approximately one atomic mass unit. -
Principles and Applications of Liquid Scintillation Counting
Principles and Applications of Liquid Scintillation Counting A PRIMER FOR ORIENTATION – National Diagnostics Laboratory Staff Principles 1.1 RADIOACTIVE EMISSIONS 1.2 MEASUREMENT OF RADIATION AND ISOTOPE QUANTITATION 1.3 MECHANISM OF LIQUID SCINTILLATION COUNTING 1.4 LIQUID SCINTILLATION SIGNAL INTERPRETATION 1.5 THE COMPLETE SCINTILLATION COCKTAIL 1.6 CHEMILUMINESCENCE AND STATIC ELECTRICITY 1.7 WASTE DISPOSAL ISSUES Applications 2.1 COUNTING DISCRETE SAMPLES 2.2 SPECIAL SAMPLE PREPARATION PROTOCOLS 2.3 FLOW LIQUID SCINTILLATION 2.4 LIQUID SCINTILLATION AND RADIATION SAFETY USA: 1-800-526-3867 © 2004 National Diagnostics EUROPE: 441 482 646022 LSC Concepts - Fundamentals of Liquid Scintillation Counting Fundamentals of Liquid 1 Scintillation Counting 1.1 RADIOACTIVE EMISSIONS 1.4 LIQUID SCINTILLATION SIGNAL Types of Radioactive Emission / Characteristics of INTERPRETATION Useful Isotopes / Use of Isotopes in Research Patterns of Light Emission / Pulse Analysis / Counting Efficiency / Quenching 1.2 MEASUREMENT OF RADIATION AND ISOTOPE QUANTITATION 1.5 THE COMPLETE SCINTILLATION Ionization Detection / Scintillation Detection COCKTAIL 1.3 MECHANISM OF LIQUID 1.6 CHEMILUMINESCENCE AND SCINTILLATION COUNTING STATIC ELECTRICITY The Role of the Solvent / The Role of Phosphors (Scintillators) 1.7 WASTE DISPOSAL ISSUES Liquid Scintillation Counting...Making Light of the Situation he chemical properties of an element are determined by its atomic number - the number of protons in the nucleus (and electrons within neutral atoms of that element). Uncharged neutrons, within the nucleus along Twith protons, do not contribute to the atomic number, but will alter the atomic mass. This makes possible the existence of isotopes, which are atoms of the same element with different atomic weight. Most isotopes are stable, and do not undergo any spontaneous nuclear changes. -
VISTA Technologies, Inc. Radiation Safety Program, Procedure
VISTA Technologies, Inc. Radiation Safety Program PROCEDURE- 19 DECONTAMINATION TECHNOLOGIES 1019 Central Parkway North, Suite 115 San Antonio, Texas 78232 210-494-4282 TABLE OF CONTENTS 1. DECONTAM IN ATION OF PERSONNEL ............................................................................. 1 1.1. Necessary Supplies ...................................................................................................... 1 1.2. Decontam ination Facilities ............................................................................................ 2 1.3. Specific Instructions ....................................................................................................... 2 2. DECONTAMINATION OF EQUIPMENT, VEHICLES, MATERIALS, AND TOOLS ....... 4 2.1. Necessary Supplies ...................................................................................................... 4 2.2. Specific Instructions ....................................................................................................... 4 2.3. Equipm ent, M aterial, and Tools ..................................................................................... 5 2.4. Vehicles .............................................................................................................................. 6 3. DECONTAM IN ATION PROCEDURES ............................................................................ 6 3.1. Pre-Decontam ination Procedures .................................................................................. 6 3.2. Establishm ent of the Decontam