Radiation Safety Training Guide for Radionuclide Users
Total Page:16
File Type:pdf, Size:1020Kb
Load more
Recommended publications
-
The Radiation Challenge Module 2: Radiation Damage in Living Organisms Educator Guide
National Aeronautics and Space Administration Space Faring The Radiation Challenge An Interdisciplinary Guide on Radiation and Human Space Flight Module 2: Radiation Damage in Living Organisms Educational Product Educators Grades and Students 9 – 12 EP-2007-08-117-MSFC Radiation Educator Guide Module 2: Radiation Damage in Living Organisms Prepared by: Jon Rask, M.S., ARC Education Specialist Wenonah Vercoutere, Ph.D., NASA ARC Subject Matter Expert Al Krause, MSFC Education Specialist BJ Navarro, NASA ARC Project Manager Space Faring: The Radiation Challenge i Table of Contents Module 2: Module 2: Radiation Damage in Living Organisms .............................................................................1 Why is NASA Studying the Biological Effects of Radiation? .........................................................1 How Do Scientists Study Biological Change During Spaceflight? .................................................1 Using Non-Human Organisms to Understand Radiation Damage ................................................2 What are the Risks and Symptoms of Radiation Exposure for Humans? .......................................3 What is DNA? ..............................................................................................................................3 What is the Structure of DNA? .....................................................................................................3 What is DNA’s Role in Protein Production? ..................................................................................4 -
Radioisotopes and Radiopharmaceuticals
RADIOISOTOPES AND RADIOPHARMACEUTICALS Radioisotopes are the unstable form of an element that emits radiation to become a more stable form — they have certain special attributes. These make radioisotopes useful in areas such as medicine, where they are used to develop radiopharmaceuticals, as well as many other industrial applications. THE PRODUCTION OF TECHNETIUM-99m RADIOPHARMACEUTICALS: ONE POSSIBLE ROUTE IRRADIATED U-235 99 TARGETS MO PROCESSING FACILITY HOSPITAL RADIOPHARMACY (MIXING WITH BIOLOGICAL MOLECULES THAT BIND AT DIFFERENT LOCATIONS IN THE 99mTC IS IDEAL FOR DIAGNOSTICS BECAUSE OF BODY, SUPPORTING A WIDE ITS SHORT HALF-LIFE (6 HOURS) AND IDEAL GAMMA EMISSION RANGE OF MEDICAL NUCLEAR APPLICATIONS) REACTOR: 6 HOURS MAKES DISTRIBUTION DIFFICULT 99MO BULK LIQUID TARGET ITS PARENT NUCLIDE, MOLYBDENUM-99, IS PRODUCED; ITS HALF-LIFE (66 HOURS) MAKES 99 99m IRRADIATION IT SUITABLE FOR TRANSPORT MO/ TC GENERATORS 99MO/99mTC GENERATORS ARE PRODUCED AND DISTRIBUTED AROUND THE GLOBE 99MO/99TC GENERATOR MANUFACTURER Radioisotopes can occur naturally or be produced artificially, mainly in research reactors and accelerators. They are used in various fields, including nuclear medicine, where radiopharmaceuticals play a major role. Radiopharmaceuticals are substances that contain a radioisotope, and have properties that make them effective markers in medical diagnostic or therapeutic procedures. The chemical presence of radiopharmaceuticals can relay detailed information to medical professionals that can help in diagnoses and treatments. Eighty percent of all diagnostic medical scans worldwide use 99mTc, and its availability, at present, is dependent on the production of 99Mo in research reactors. Globally, the number of medical procedures involving the use of radioisotopes is growing, with an increasing emphasis on radionuclide therapy using radiopharmaceuticals for the treatment of cancer.. -
OPERATIONAL GUIDANCE on HOSPITAL RADIOPHARMACY: a SAFE and EFFECTIVE APPROACH the Following States Are Members of the International Atomic Energy Agency
OPERATIONAL GUIDANCE ON HOSPITAL RADIOPHARMACY: A SAFE AND EFFECTIVE APPROACH The following States are Members of the International Atomic Energy Agency: AFGHANISTAN GUATEMALA PAKISTAN ALBANIA HAITI PALAU ALGERIA HOLY SEE PANAMA ANGOLA HONDURAS PARAGUAY ARGENTINA HUNGARY PERU ARMENIA ICELAND PHILIPPINES AUSTRALIA INDIA POLAND AUSTRIA INDONESIA PORTUGAL AZERBAIJAN IRAN, ISLAMIC REPUBLIC OF QATAR BANGLADESH IRAQ REPUBLIC OF MOLDOVA BELARUS IRELAND ROMANIA BELGIUM ISRAEL RUSSIAN FEDERATION BELIZE ITALY SAUDI ARABIA BENIN JAMAICA SENEGAL BOLIVIA JAPAN SERBIA BOSNIA AND HERZEGOVINA JORDAN SEYCHELLES BOTSWANA KAZAKHSTAN BRAZIL KENYA SIERRA LEONE BULGARIA KOREA, REPUBLIC OF SINGAPORE BURKINA FASO KUWAIT SLOVAKIA CAMEROON KYRGYZSTAN SLOVENIA CANADA LATVIA SOUTH AFRICA CENTRAL AFRICAN LEBANON SPAIN REPUBLIC LIBERIA SRI LANKA CHAD LIBYAN ARAB JAMAHIRIYA SUDAN CHILE LIECHTENSTEIN SWEDEN CHINA LITHUANIA SWITZERLAND COLOMBIA LUXEMBOURG SYRIAN ARAB REPUBLIC COSTA RICA MADAGASCAR TAJIKISTAN CÔTE D’IVOIRE MALAWI THAILAND CROATIA MALAYSIA THE FORMER YUGOSLAV CUBA MALI REPUBLIC OF MACEDONIA CYPRUS MALTA TUNISIA CZECH REPUBLIC MARSHALL ISLANDS TURKEY DEMOCRATIC REPUBLIC MAURITANIA UGANDA OF THE CONGO MAURITIUS UKRAINE DENMARK MEXICO UNITED ARAB EMIRATES DOMINICAN REPUBLIC MONACO UNITED KINGDOM OF ECUADOR MONGOLIA GREAT BRITAIN AND EGYPT MONTENEGRO NORTHERN IRELAND EL SALVADOR MOROCCO ERITREA MOZAMBIQUE UNITED REPUBLIC ESTONIA MYANMAR OF TANZANIA ETHIOPIA NAMIBIA UNITED STATES OF AMERICA FINLAND NEPAL URUGUAY FRANCE NETHERLANDS UZBEKISTAN GABON NEW ZEALAND VENEZUELA GEORGIA NICARAGUA VIETNAM GERMANY NIGER YEMEN GHANA NIGERIA ZAMBIA GREECE NORWAY ZIMBABWE The Agency’s Statute was approved on 23 October 1956 by the Conference on the Statute of the IAEA held at United Nations Headquarters, New York; it entered into force on 29 July 1957. The Headquarters of the Agency are situated in Vienna. -
Chapter 1.2: Transformation Kinetics
Chapter 1: Radioactivity Chapter 1.2: Transformation Kinetics 200 NPRE 441, Principles of Radiation Protection Chapter 1: Radioactivity http://www.world‐nuclear.org/info/inf30.html 201 NPRE 441, Principles of Radiation Protection Chapter 1: Radioactivity Serial Transformation In many situations, the parent nuclides produce one or more radioactive offsprings in a chain. In such cases, it is important to consider the radioactivity from both the parent and the daughter nuclides as a function of time. • Due to their short half lives, 90Kr and 90Rb will be completely transformed, results in a rapid building up of 90Sr. • 90Y has a much shorter half‐life compared to 90Sr. After a certain period of time, the instantaneous amount of 90Sr transformed per unit time will be equal to that of 90Y. •Inthiscase,90Y is said to be in a secular equilibrium. 202 NPRE 441, Principles of Radiation Protection Chapter 1: Radioactivity Exponential DecayTransformation Kinetics • Different isotopes are characterized by their different rate of transformation (decay). • The activity of a pure radionuclide decreases exponentially with time. For a given sample, the number of decays within a unit time window around a given time t is a Poisson random variable, whose expectation is given by t Q Q0e •Thedecayconstant is the probability of a nucleus of the isotope undergoing a decay within a unit period of time. 203 NPRE 441, Principles of Radiation Protection Chapter 1: Radioactivity Why Exponential Decay? The decay rate, A, is given by Separate variables in above equation, we have The decay constant is the probability of a nucleus of the isotope undergoing a decay within a unit period of time. -
Experimental Γ Ray Spectroscopy and Investigations of Environmental Radioactivity
Experimental γ Ray Spectroscopy and Investigations of Environmental Radioactivity BY RANDOLPH S. PETERSON 216 α Po 84 10.64h. 212 Pb 1- 415 82 0- 239 β- 01- 0 60.6m 212 1+ 1630 Bi 2+ 1513 83 α β- 2+ 787 304ns 0+ 0 212 α Po 84 Experimental γ Ray Spectroscopy and Investigations of Environmental Radioactivity Randolph S. Peterson Physics Department The University of the South Sewanee, Tennessee Published by Spectrum Techniques All Rights Reserved Copyright 1996 TABLE OF CONTENTS Page Introduction ....................................................................................................................4 Basic Gamma Spectroscopy 1. Energy Calibration ................................................................................................... 7 2. Gamma Spectra from Common Commercial Sources ........................................ 10 3. Detector Energy Resolution .................................................................................. 12 Interaction of Radiation with Matter 4. Compton Scattering............................................................................................... 14 5. Pair Production and Annihilation ........................................................................ 17 6. Absorption of Gammas by Materials ..................................................................... 19 7. X Rays ..................................................................................................................... 21 Radioactive Decay 8. Multichannel Scaling and Half-life ..................................................................... -
Influence of Radiation Damage on Xenon Diffusion in Silicon Carbide
Influence of radiation damage on xenon diffusion in silicon carbide E. Friedland*a, K. Gärtnerb, T.T. Hlatshwayoa, N.G. van der Berga, T.T. Thabethea a Physics Department, University of Pretoria, Pretoria, South Africa b Institut für Festkörperphysik, Friedrich-Schiller-Universität, Jena, Germany Keywords silicon carbide, diffusion, radiation damage *Corresponding author. E mail: [email protected], Phone: +27-12-4202453, Fax: +27-12-3625288 Diffusion of xenon in poly and single crystalline silicon carbide and the possible influence of radiation damage on it are investigated. For this purpose 360 keV xenon ions were implanted in commercial 6H-SiC and CVD-SiC wafers at room temperature, 350 °C and 600 °C. Width broadening of the implantation pro- files and xenon retention during isochronal and isothermal annealing up to temperatures of 1500 °C was de- termined by RBS-analysis, whilst in the case of 6H-SiC damage profiles were simultaneously obtained by a- particle channelling. No diffusion or xenon loss was detected in the initially amorphized and eventually re- crystallized surface layer of cold implanted 6H-SiC during annealing up to 1200 °C. Above that temperature serious erosion of the implanted surface occurred, which made any analysis impossible. No diffusion or xen- on loss is detected in the hot implanted 6H-SiC samples during annealing up to 1400 °C. Radiation damage dependent grain boundary diffusion is observed at 1300 °C in CVD-SiC. 1 Introduction Modern high-temperature nuclear reactors (HTR’s) commonly use fuel elements containing triple isotropic cladded (TRISO) fuel particles. These are fuel kernels surrounded by four successive lay- ers of low-density pyrolitic carbon, high-density pyrolitic carbon, silicon carbide and high-density pyrolitic carbon, with silicon carbide being the main barrier to prevent the release of fission prod- ucts. -
Nuclide Safety Data Sheet Iron-59
59 Nuclide Safety Data Sheet 59 Iron-59 Fe www.nchps.org Fe I. PHYSICAL DATA 1 Gammas/X-rays: 192 keV (3% abundance); 1099 keV (56%), 1292 keV (44%) Radiation: 1 Betas: 131 keV (1%), 273 keV (46%), 466 keV (53%) 2 Gamma Constant: 0.703 mR/hr per mCi @ 1.0 meter [1.789E-4 mSv/hr per MBq @ 1.0 meter] 1 Half-Life [T½] : Physical T½: 44.5 day 3 Biological T½: ~1.7 days (ingestion) ; much longer for small fraction Effective T½: ~1.7 days (varies; also small fraction retained much longer) Specific Activity: 4.97E5 Ci/g [1.84E15 Bq/g] max.1 II. RADIOLOGICAL DATA Radiotoxicity4: 1.8E-9 Sv/Bq (67 mrem/uCi) of 59Fe ingested [CEDE] 4.0E-9 Sv/Bq (150 mrem/uCi) of 59Fe inhaled [CEDE] Critical Organ: Spleen1, [blood] Intake Routes: Ingestion, inhalation, puncture, wound, skin contamination (absorption); Radiological Hazard: Internal Exposure; Contamination III. SHIELDING Half Value Layer [HVL] Tenth Value Layer [TVL] Lead [Pb] 15 mm (0.59 inches) 45 mm (1.8 inches) Steel 35 mm (1.4 inches) 91 mm (3.6 inches) The accessible dose rate should be background but must be < 2 mR/hr IV. DOSIMETRY MONITORING - Always wear radiation dosimetry monitoring badges [body & ring] whenever handling 59Fe V. DETECTION & MEASUREMENT Portable Survey Meters: Geiger-Mueller [e.g. PGM] to assess shielding effectiveness & contamination Wipe Test: Liquid Scintillation Counter, Gamma Counter VI. SPECIAL PRECAUTIONS • Avoid skin contamination [absorption], ingestion, inhalation, & injection [all routes of intake] • Use shielding (lead) to minimize exposure while handling of 59Fe • Use tools (e.g. -
High Altitude Nuclear Detonations (HAND) Against Low Earth Orbit Satellites ("HALEOS")
High Altitude Nuclear Detonations (HAND) Against Low Earth Orbit Satellites ("HALEOS") DTRA Advanced Systems and Concepts Office April 2001 1 3/23/01 SPONSOR: Defense Threat Reduction Agency - Dr. Jay Davis, Director Advanced Systems and Concepts Office - Dr. Randall S. Murch, Director BACKGROUND: The Defense Threat Reduction Agency (DTRA) was founded in 1998 to integrate and focus the capabilities of the Department of Defense (DoD) that address the weapons of mass destruction (WMD) threat. To assist the Agency in its primary mission, the Advanced Systems and Concepts Office (ASCO) develops and maintains and evolving analytical vision of necessary and sufficient capabilities to protect United States and Allied forces and citizens from WMD attack. ASCO is also charged by DoD and by the U.S. Government generally to identify gaps in these capabilities and initiate programs to fill them. It also provides support to the Threat Reduction Advisory Committee (TRAC), and its Panels, with timely, high quality research. SUPERVISING PROJECT OFFICER: Dr. John Parmentola, Chief, Advanced Operations and Systems Division, ASCO, DTRA, (703)-767-5705. The publication of this document does not indicate endorsement by the Department of Defense, nor should the contents be construed as reflecting the official position of the sponsoring agency. 1 Study Participants • DTRA/AS • RAND – John Parmentola – Peter Wilson – Thomas Killion – Roger Molander – William Durch – David Mussington – Terry Heuring – Richard Mesic – James Bonomo • DTRA/TD – Lewis Cohn • Logicon RDA – Les Palkuti – Glenn Kweder – Thomas Kennedy – Rob Mahoney – Kenneth Schwartz – Al Costantine – Balram Prasad • Mission Research Corp. – William White 2 3/23/01 2 Focus of This Briefing • Vulnerability of commercial and government-owned, unclassified satellite constellations in low earth orbit (LEO) to the effects of a high-altitude nuclear explosion. -
How Do Radioactive Materials Move Through the Environment to People?
5. How Do Radioactive Materials Move Through the Environment to People? aturally occurring radioactive materials Radionuclides can be removed from the air in Nare present in our environment and in several ways. Particles settle out of the our bodies. We are, therefore, continuously atmosphere if air currents cannot keep them exposed to radiation from radioactive atoms suspended. Rain or snow can also remove (radionuclides). Radionuclides released to them. the environment as a result of human When these particles are removed from the activities add to that exposure. atmosphere, they may land in water, on soil, or Radiation is energy emitted when a on the surfaces of living and non-living things. radionuclide decays. It can affect living tissue The particles may return to the atmosphere by only when the energy is absorbed in that resuspension, which occurs when wind or tissue. Radionuclides can be hazardous to some other natural or human activity living tissue when they are inside an organism generates clouds of dust containing radionu- where radiation released can be immediately clides. absorbed. They may also be hazardous when they are outside of the organism but close ➤ Water enough for some radiation to be absorbed by Radionuclides can come into contact with the tissue. water in several ways. They may be deposited Radionuclides move through the environ- from the air (as described above). They may ment and into the body through many also be released to the water from the ground different pathways. Understanding these through erosion, seepage, or human activities pathways makes it possible to take actions to such as mining or release of radioactive block or avoid exposure to radiation. -
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 .