Guide for Radiological Laboratories for the Control of Radioactive Contamination and Radiation Exposure
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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 . -
Personal Radiation Monitoring
Personal Radiation Monitoring Tim Finney 2020 Radiation monitoring Curtin staff and students who work with x-ray machines, neutron generators, or radioactive substances are monitored for exposure to ionising radiation. The objective of radiation monitoring is to ensure that existing safety procedures keep radiation exposure As Low As Reasonably Achievable (ALARA). Personal radiation monitoring badges Radiation exposure is measured using personal radiation monitoring badges. Badges contain a substance that registers how much radiation has been received. Here is the process by which a user’s radiation dose is measured: 1. The user is given a badge to wear 2. The user wears the badge for a set time period (usually three months) 3. At the end of the set time, the user returns the badge 4. The badge is sent away to be read 5. A dose report is issued. These steps are repeated until monitoring is no longer required. Badges are supplied by a personal radiation monitoring service provider. Curtin uses a service provider named Landauer. In addition to user badges, the service provider sends control badges that are kept on site in a safe place away from radiation sources. The service provider reads each badge using a process that extracts a signal from the substance contained in the badge to obtain a dose measurement. (Optically stimulated luminescence is one such process.) The dose received by the control badge is subtracted from the user badge reading to obtain the user dose during the monitoring period. Version 1.0 Uncontrolled document when printed Health and Safety Page 1 of 7 A personal radiation monitoring badge Important Radiation monitoring badges do not protect you from radiation exposure. -
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. -
小型飛翔体/海外 [Format 2] Technical Catalog Category
小型飛翔体/海外 [Format 2] Technical Catalog Category Airborne contamination sensor Title Depth Evaluation of Entrained Products (DEEP) Proposed by Create Technologies Ltd & Costain Group PLC 1.DEEP is a sensor analysis software for analysing contamination. DEEP can distinguish between surface contamination and internal / absorbed contamination. The software measures contamination depth by analysing distortions in the gamma spectrum. The method can be applied to data gathered using any spectrometer. Because DEEP provides a means of discriminating surface contamination from other radiation sources, DEEP can be used to provide an estimate of surface contamination without physical sampling. DEEP is a real-time method which enables the user to generate a large number of rapid contamination assessments- this data is complementary to physical samples, providing a sound basis for extrapolation from point samples. It also helps identify anomalies enabling targeted sampling startegies. DEEP is compatible with small airborne spectrometer/ processor combinations, such as that proposed by the ARM-U project – please refer to the ARM-U proposal for more details of the air vehicle. Figure 1: DEEP system core components are small, light, low power and can be integrated via USB, serial or Ethernet interfaces. 小型飛翔体/海外 Figure 2: DEEP prototype software 2.Past experience (plants in Japan, overseas plant, applications in other industries, etc) Create technologies is a specialist R&D firm with a focus on imaging and sensing in the nuclear industry. Createc has developed and delivered several novel nuclear technologies, including the N-Visage gamma camera system. Costainis a leading UK construction and civil engineering firm with almost 150 years of history. -
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. -
G20070354/G20070331 Fact Sheet, Biological Effects of Radiation
Fact Sheet 11 Ofice of Public Affairs Telephone: 301/415-8200 E-mail : opa @nrc.g ov I Biological Effects of Radiation Background Radiation is all around us. It is naturally present in our environment and has been since the birth of this planet. Consequently, life has evolved in an environment which has significant levels of ionizing radiation. It comes from outer space (cosmic), the ground (terrestrial), and even from within our own bodies. It is present in the air we breathe, the food we eat, the water we drink, and in the construction materials used to build our homes. Certain foods such as bananas and brazil nuts naturally contain higher levels of radiation than other foods. Brick and stone homes have higher natural radiation levels than homes made of other building materials such as wood. Our nation's Capitol, which is largely constructed of granite, contains higher levels of natural radiation than most homes. Levels of natural or background radiation can vary greatly from one location to the next. For example, people residing in Colorado are exposed to more natural radiation than residents of the east or west coast because Colorado has more cosmic radiation at a higher altitude and more terrestrial radiation from soils enriched in naturally occurring uranium. Furthermore, a lot of our natural exposure is due to radon, a gas from the earth's crust that is present in the air we breathe. The average annual radiation exposure from natural sources to an individual in the United States is about 300 millirem (3 millisieverts)*. Radon gas accounts for two-thirds of this exposure, while cosmic, terrestrial, and internal radiation account for the remainder. -
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. -
RADIOACTIVE MATERIALS SECTION Revisions 3 and 4 Filing Instructions
Jeb Bush John O. Agwunobi, M.D., M.B.A Governor Acting Secretary August 2001 Bureau of Radiation Control RADIOACTIVE MATERIALS SECTION Information Notice 2001-04 Revisions 3 and 4 Filing Instructions: Changes to Chapter 64E-5, Florida Administrative Code (F.A.C.) Changes were made to “Control of Radiation Hazard Regu lations,” Chapter 64E-5, F.A.C., that became effective August 8 and September 11, 2001. These changes are indicated as Revision 3 or (R3) and Revision 4 (R4) in the margin. Enclosed are copies of the pages to be inserted. This update is printed on blue paper. These instructions apply to the complete version (brown cover) of Chapter 64E -5, F.A.C. Be sure that Revision 1 and Revision 2 changes have been made before making these changes. This can be verified by checking page ii of the index. PART PAGES TO BE REMOVED PAGES TO BE INSERTED Page Number Page Number Index i through xii i through xii I Part I Index Part I Index General Provisions I-1 through I-22 I-1 through I-22 II Part II Index Part II Index Licensing of Radioactive II-45 through II-46 II-45 through II-46 Materials II-53 through II-54 II-53 through II-54 IV Part IV Index Part IV Index Radiation Safety Requirements IV-1 through IV-16 IV-1 through IV-24 for Industrial Radiographic Operations VI Part VI Index Part VI Index Use of Radionuclides in the VI-1 through VI-2 VI-1 through VI-2 Healing Arts VI-5 through VI-6 VI-5 through VI-6 VI-23 through VI-26 VI-23 through VI-26 Attachment Attachment page not Attachment not numbered Certificate – Disposition of numbered (mailing -
Release of Patients Administered Radioactive Materials
NEW YORK STATE DEPARTMENT OF HEALTH BUREAU OF ENVIRONMENTAL RADIATION PROTECTION DRAFT RADIATION GUIDE 10.17 RELEASE OF PATIENTS ADMINISTERED RADIOACTIVE MATERIALS A. INTRODUCTION Section 16.123(b) of 10 NYCRR Part 16 requires licensees to assess the radiation exposure to individuals from patients administered radioactive materials and take action, as appropriate, to reduce exposures to other individuals. These requirements apply for both diagnostic and therapeutic uses regardless of the amount administered. Section 16.123(b), Medical uses of radioactive material, states: P The licensee shall confine patients undergoing procedures authorized by ...until the total effective dose equivalent for the individuals (other than the patient) likely to receive the greatest dose is 5 mSv (500 mrem) or less. P When the total effective dose equivalent to any individual that could result from the release of a patient is likely to exceed 1 mSv (100 mrem), the licensee shall: • provide the patient, or his/her competent representative, written information on risks of radiation and methods for reducing the exposure of individuals; and • keep records of such patients release for a period of five years. This document is designed to provide guidance on determining the potential dose to an individual likely to receive the highest dose from exposure to the patient, to establish appropriate activities and dose rates for release, to provide guidelines for instructions to patients on how to reduce exposures to other individuals, to describe recordkeeping requirements, and to inform licensees of other potential problems associated with the release of patients containing radioactive materials. B. DISCUSSION The radiation dose to another individual from a patient is highly dependent on a number of factors, including the amount and type of radioactive material administered, the patient's living/working arrangements, ability/willingness to follow instructions, etc. -
Radiation Sources- Radiating Health and Progress…
RADIATION SOURCES- RADIATING HEALTH AND PROGRESS…. ….. BUT NEED REGULATION NEVERTHELESS!!! Anuradha V ATOMIC ENERGY REGULATORY BOARD Contents- The four W’s What are radiation sources? Where are they used? Why do we need them? When is their use dangerous and how to overcome this? 3 Applications of Radiation- All areas of life Medical- Diagnosis and treatment Industrial- Food processing, Radiography, Gauges and measurement Research – Irradiation of samples, Calibration sources, tracers Agriculture- Tracer studies MEDICAL USES RADIOTHERAPY INTERVENTIONAL RADIOLOGY RADIO-PHARMACEUTICALS COMPUTED TOMOGRAPHY BLOOD/TISSUE IRRADIATOR INDUSTRIAL USES FOOD IRRADIATION INDUSTRIAL RADIOGRAPHY NUCLEONIC GAUGES RESEARCH TRACER STUDY IRRADIATION OF SAMPLES Department of Atomic Energy Atomic Department of Image courtesy: courtesy: Image Alexander L.- Polonium poisoning of Russian spy Atomic bomb survivors “RADIATION GOOGLE IS INDEED DISASTROUS” Image courtesy: socialistworld.net Image courtesy: courtesy: Image THE QUESTION TO ASK IS NOT "IS THERE ANY RADIOACTIVITY PRESENT?" BUT RATHER, "HOW MUCH, AND IS IT ENOUGH TO BE HARMFUL?" Atomic Energy Regulatory Board, Anushakti nagar Mumbai 10 Safety Research Institute at Kalpakkam Regional Centers at Chennai, New Delhi and Kolkata Effects Linear- Non Threshold model for Radiation AERB mandates in this area for safety DNA damage reduction CANCER RISK Epilation Erythema GI/ CNS Symptoms area for Prevention Prevention area for Death mandates in this AERB These effects are more profound in the foetus and children “Licence in accordance with Atomic Energy (Radiation Protection)Rules, 2004 from AERB is mandatory requirement for the procurement and use of radiation sources in India”. 12 Safety Research funding Safety in application of nuclear and radiation facilities Environmental Impact Assessment Transport of Radioactive material Radioactive Waste Management Civil and Structural Engineering Spent Fuel Storage Reactor Physics Thermal Hydraulics/Fluid Structure Interactions in Reactors under Accident Conditions . -
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. -
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.