Appendix B: Recommended Procedures
Total Page:16
File Type:pdf, Size:1020Kb
Load more
Recommended publications
-
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 . -
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. -
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. -
Ionization Chamber Type Survey Instruments
Chapter 5: Instrumentation Objectives: • Summarize the advantages and disadvantages of the different types of devices used to monitor individuals for radiation exposure. • Describe the principal advantages and disadvantages of air ionization chamber type survey instruments. • Describe the principal advantages and disadvantages of Geiger-Müller (GM) type survey instruments. SAT Chapter 5 - Instrumentation 2 Objectives: • Describe the important characteristics of any radiation monitoring instrument and why these characteristics are important for obtaining accurate results. • Select the appropriate survey instrument for a task, and be able to ensure its proper operation and be able to interpret the results obtained. SAT Chapter 5 - Instrumentation 3 Overview: • Humans cannot detect ionizing radiation with any of our senses. But, we need to know: – Is ionizing radiation present? – Are we receiving dose from ionizing radiation? – How much dose have we received (mrem)? – Is there contamination present? • We use instruments which respond to ionizing radiation. The type of instrument needed depends on the type and levels of radiation that are present. • Radiation detectors respond to ionizations or excitations created by radiation interaction with the detector media. Detectors can either be gas-filled or solid materials. SAT Chapter 5 - Instrumentation 4 Instrumentation Gas-filled instruments for detecting ionizing radiation utilize the concept that radiation interaction with atoms can cause ionizations. The ions are collected and measured. This is used to provide information on the presence of radioactive material (contamination) or the dose rate in an area. Hi + Volt - Ionizing Radiation (MEDIUM) SAT Chapter 5 - Instrumentation 5 IONIZATION CURVE 1015 I II III IV V VI 1012 Proportional 109 Continuous Geiger- Discharge Müller 106 α # of Ion Pairs Collected Pairs Ion of # 103 β 0 0 200 400 600 800 1000 1200 1400 1600 Applied Voltage, V SAT Chapter 5 - Instrumentation 6 Ionization Chamber Ionization chambers measure the ionization of air. -
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. -
Thermo Micro Rem / Micro Sievert Tissue Equivalent Survey Meters
A D V A N C E D T E C H N O L O G Y F O R A S A F E R W O R L D Micro Rem/Sievert Tissue Equivalent Survey Meter The Micro Rem and Micro Sievert models are lightweight, portable survey meters for applications where accurate dose rate measurements of low radiation levels are required. Accurate down to background levels, the Micro Rem and Micro Sievert read absorbed dose rate directly so no conversion from mR/h is required. APPLICATIONS The tissue-equivalent scintillator used in the Micro Rem and Micro Sievert gives them a nearly flat, rem energy response. This rem response is based • Routine low/medium level gamma dose rate on the deep dose equivalent index for 1 cm (0.39”) depth, uniparallel surveys directional beam as calculated on the ICRU standard sphere. • Confirming radiation boundaries • Monitoring items for unrestricted release These instruments give tissue equivalent photon response for x-ray and • X-ray surveys, using the expanded low gamma radiation from environmental levels of 0-20 μrem/h (o-0.2 μ Sv/h) energy range option full scale up to normal survey levels of 200 mrem/h (2 mSv/h) full scale. Rugged construction and quality components make the Micro Rem and Options Micro Sievert durable, and they are easy to service. Internal components You can “customize” your instrument with practical are laid out on modular circuit boards. Span, HV and calibration pots (one options to match the requirements of your survey for each range) are clearly marked. -
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. -
Radioactive Materials Transportation and Incident Response
RADIOACTIVE MATERIALS TRANSPORTATION AND INCIDENT RESPONSE U.S. Department of Energy Transportation Emergency Preparedness Program Q&A About Incident Response 04/12 QA Phone Number Radio Frequency Law Enforcement ____________________________________ RADIOACTIVE Fire ___________________________________________ MATERIALS Medical ____________________________________________ TRANSPORTATION AND INCIDENT RESPONSE State Radiological Assistance ___________________________ Local Government Official ______________________________ Local Emergency Management Agency ___________________ State Emergency Management Agency ___________________ HAZMAT Team ______________________________________ Water Pollution Control ________________________________ CHEMTEL (Toll-free US & Canada) 1-800-255-3924 _________ CHEMTREC (Toll-free US & Canada) 1-800-424-9300 _______ CHEMTREC (Outside US) 1-703-527-3887 ________________ National Response Center (Toll-free US & Canada) 1-800-424-8802 ____________ In Washington, D.C. 1-202-267-2675 _____________________ Military Shipments (DoD) Call Collect 1-703-697-0218 _______ Other: ______________________________________________ Other: ______________________________________________ QQ&A About Incident Response NOTES TABLE OF CONTENTS What is radiation?.................................................................................... 2 ______________________________________________ What is radiation exposure? .................................................................... 3 ______________________________________________ -
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. -
Liquid Scintillation Counting Techniques for the Determination of Some Alpha Emitting Actinides : a Review
2 LIQUID SCINTILLATION COUNTING TECHNIQUES FOR THE DETERMINATION OF SOME ALPHA EMITTING ACTINIDES : A REVIEW N.N.Mirashi, Keshav Chander and S.K.Aggarwal Fuel Chemistry Division, Bhabha Atomic Research Center, Mumbai - 400085. 1. INTRODUCTION Liquid scintillation process is based on the conversion of a part of the kinetic energy of alpha / beta / gamma radiation into photons. The photons are counted and related to the concentration of alpha/beta/gamma emitter. The principal use of liquid scintillation counting was the assay of low energy beta emitting nuclides. Alpha emitters could be counted by liquid scintillation counting was also known for long [1]. Alpha emitters, in spite of much lower scintillation yield compared to beta particles, are much more easily counted than beta particles, because alpha particles emit a line spectrum whereas beta spectrum is a continuum. The use of liquid scintillation counting is attractive because of its 100% counting efficiency and simplicity of sample preparation. Alpha particle assay by conventional plate counting methods is difficult because of chemical separation losses and/or self-absorption losses in the final sample may cause either non-reproducible results or create unacceptable errors. Several workers made applications of liquid scintillation counting technique to alpha counting in late 1950s and early 1960s [2-6]; still because of high background, interference from beta particles and very poor energy resolution for alpha energies liquid scintillation counting was not widespread for alpha counting. Horrocks [6] and Ihle et al [7] obtained a good degree of alpha energy resolution by liquid scintillation technique. This has led to identification and determination of mixture of alpha emitters.