Radiation Dose and the Biological Effect of Ionising Radiation
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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. -
Nuclear Radiation 1. an Atom Contains Electrons, Protons and Neutrons
Nuclear Radiation 1. An atom contains electrons, protons and neutrons. Which of these particles a) are outside the nucleus b) are uncharged c) have a negative charge d) are nucleons e) are much lighter than the others? 2. Complete the table below. Name Symbol Charge What is it? Alpha particle β -1 Gamma ray An electromagnetic wave 3. How is an ionised material different from a material that is not ionised? National 5 Physics: Waves & Radiation 1 Absorption of Radiation 1. The figure below shows a Geiger tube used to detect radiation from a radioactive source. thick lead plate 0 4 2 5 start counter stop ON OFF reset Geiger tube radioactive source The following measurements were made using the apparatus above. Counts in 300 seconds Readings Average 1 No source present 102 94 110 2 Source present at fixed distance from tube a) No lead plate present 3466 3420 3410 b) Thick lead plate present 105 109 89 c) Aluminium sheet in place of the 1834 1787 1818 thick lead sheet a) Complete the table by calculating the average readings. b) Why are the readings on each line not the same? c) What can you say from the table about the effect on the radiation of: i. The lead plate? ii. The aluminium plate? d) Why is it possible to say from the readings that: i. gamma radiation is emitted by the source? ii. alpha and beta radiation might be emitted by the source? e) What further tests could you make using this arrangement to find out whether or not the source emits alpha radiation? National 5 Physics: Waves & Radiation 2 2. -
Copyright by Arthur Bryan Crawford 2004
Copyright by Arthur Bryan Crawford 2004 The Dissertation Committee for Arthur Bryan Crawford Certifies that this is the approved version of the following dissertation: Evaluation of the Impact of Non -Uniform Neutron Radiation Fields on the Do se Received by Glove Box Radiation Workers Committee: Steven Biegalski, Supervisor Sheldon Landsberger John Howell Ofodike Ezekoye Sukesh Aghara Evaluation of the Impact of Non -Uniform Neutron Radiation Fields on the Dose Received by Glove Box Radiation Workers by Arthur Bryan Crawford, B.S., M.S. Dissertation Presented to the Faculty of the Graduate School of The University of Texas at Austin in Partial Fulfillment of the Requirements for the Degree of Doctor of Philosophy The University of Texas at Austin December, 2004 Dedication I was born to goodly parents Harvey E. Crawford and Johnnie Lee Young Crawford Acknowledgements I would like to express my gratitude to Dr. Sheldon Landsberger for his vision in starting a distance learning program at the University of Texas at Austin and for his support and encouragement on this quest. I would like to thank my advisor, Dr. Steven Biegalski, for his support and encouragement even though the topic area was new to him. I would like to thank the members of my dissertation committee for finding the time to review this dissertation. To the staff of the Nuclear Engineering Teaching Laboratory I say thank you for your kindness and support during those brief times that I was on cam pus. A special thanks to my past and present group leaders, David Seidel, Eric McNamara, and Bill Eisele and my Division Leader, Lee McAtee, at Los Alamos National Laboratory, for their support in being allowed to use time and material resources at the Lab oratory and for financial support in the form of tuition reimbursement and travel expenses. -
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. -
Occupational Radiation Protection Record-Keeping and Reporting Guide
DOE G 441.1-11 (formerly G-10 CFR 835/H1) 05-20-99 OCCUPATIONAL RADIATION PROTECTION RECORD-KEEPING AND REPORTING GUIDE for use with Title 10, Code of Federal Regulations, Part 835, Occupational Radiation Protection Assistant Secretary for Environment, Safety and Health (THIS PAGE INTENTIONALLY LEFT BLANK) DOE G 441.1-11 i 05-20-99 CONTENTS CONTENTS PAGE 1. PURPOSE AND APPLICABILITY ........................................................ 1 2. DEFINITIONS ........................................................................ 2 3. DISCUSSION ........................................................................ 3 4. IMPLEMENTATION GUIDANCE ......................................................... 4 4.1 RECORDS TO BE GENERATED AND MAINTAINED ................................ 4 4.1.1 Individual Monitoring and Dose Records ........................................ 4 4.1.2 Monitoring and Workplace Records ............................................ 8 4.1.3 Administrative Records .................................................... 11 4.2 REPORTS ................................................................... 15 4.2.1 Reports to Individuals ...................................................... 16 4.2.2 Reports of Planned Special Exposures ......................................... 17 4.3 PRIVACY ACT CONSIDERATIONS .............................................. 17 4.3.1 Informing Individuals ...................................................... 17 4.3.2 Identifying Individuals ..................................................... 17 -
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). -
Rapport Du Groupe De Travail N° 9 Du European Radiation Dosimetry Group (EURADOS) – Coordinated Network for Radiation Dosimetry (CONRAD – Contrat CE Fp6-12684)»
- Rapport CEA-R-6220 - CEA Saclay Direction de la Recherche Technologique Laboratoire d’Intégration des Systèmes et des Technologies Département des Technologies du Capteur et du Signal Laboratoire National Henri Becquerel RADIATION PROTECTION DOSIMETRY IN MEDECINE REPORT OF THE WORKING GROUP N° 9 OF THE EUROPEAN RADIATION DOSIMETRY GROUP (EURADOS) COORDINATED NETWORK FOR RADIATION DOSIMETRY (CONRAD – CONTRACT EC N° FP6-12684) - Juin 2009 - RAPPORT CEA-R-6220 – «Dosimétrie pour la radioprotection en milieu médical – Rapport du groupe de travail n° 9 du European Radiation Dosimetry group (EURADOS) – Coordinated Network for Radiation Dosimetry (CONRAD – contrat CE fp6-12684)» Résumé - Ce rapport présente les résultats obtenus dans le cadre des travaux du WP7 (dosimétrie en radioprotection du personnel médical) de l’action coordonnée CONRAD (Coordinated Network for Radiation Dosimetry) subventionné par la 6ème FP de la communauté européenne. Ce projet a été coordonné par EURADOS (European RadiationPortection group). EURADOS est une organisation fondée en 1981 pour promouvoir la compréhension scientifique et le développement des techniques de la dosimétrie des rayonnements ionisant dans les domaines de la radioprotection, de la radiobiologie, de la thérapie radiologique et du diagnostic médical ; cela en encourageant la collaboration entre les laboratoires européens. Le WP7 de CONRAD coordonne et favorise la recherche européenne pour l'évaluation des expositions professionnelles du personnel sur les lieux de travail de radiologie thérapeutique et diagnostique. La recherche est organisée en sous-groupes couvrant trois domaines spécifiques : 1. Dosimétrie d'extrémité en radiologie interventionnelle et médecine nucléaire : ce sous- groupe coordonne des investigations dans les domaines spécifiques des hôpitaux et des études de répartition des doses dans différentes parties des mains, des bras, des jambes et des pieds ; 2. -
Cost-Benefit Analysis and Radiation Protection* by J.U
Cost-Benefit Analysis and Radiation Protection* by J.U. Ahmed and H.T. Daw Cost-benefit analysis is a tool to find the best way of allocating resources. The International Commission on Radiological Protection (ICRP), in its publication No. 26, recommends this method in justifying radiation exposure practices and in keeping exposures as low as is reasonably achievable, economic and social considerations being taken into account 1. BASIC PHILOSOPHY A proposed practice involving radiation exposure can be justified by considering its benefits and its costs The aim is to ensure a net benefit. This can be expressed as: B = V-(P + X +Y) where: B is the net benefit; V is the gross benefit; P is the basic production cost, excluding protection; X is the cost of achieving the selected level of protection; and Y is the cost assigned to the detriment involved in the practice. If B is negative, the practice cannot be justified. The practice becomes increasingly justifiable at increasing positive values of B However, some of the benefits and detriments are intangible or subjective and not easily quantified. While P and X costs can be readily expressed in monetary terms, V may contain components difficult to quantify. The quantification of Y is the most problematic and probably the most controversial issue. Thus value judgements have to be introduced into the cost-benefit analysis. Such judgements should reflect the interests of society and therefore require the participation of competent authorities and governmental bodies as well as representative views of various sectors of the public. Once a practice has been justified by a cost-benefit analysis, the radiation exposure of individuals and populations resulting from that practice should be kept as low as reasonably achievable, economic and social factors being taken into account (i.e. -
Sievert Roofing Products Catalog
Heating tools for professionals Distributed by: BEST MATERIALS LLC Ph: 1-800-474-7570, 1-602-272-8128 Fax: 1-602-272-8014 Email: [email protected] www.bestmaterials.com Roofing Catalog Sievert Industries, Inc. Edition 9 Sievert Industries, Inc. In 1882, the Swedish inventor, Carl Richard Nyberg The Leader in Torch worked in his kitchen to design a revolutionary product, Technolog since1882 a vaporization torch for petrol. During the same year, he obtained a patent for his product which he called a “blow lamp”. This “blow lamp,” or torch, was distributed throughout the world with the help of the famous industrialist, Max Sievert. Carrying on Max Sievert’s work ethic, Sievert Industries, Inc. continually strives to be the leader in the North and South American roofing market since our entrance in 1996. Our goal is to provide our valued customers with quality service, competitive pricing, and the highest level of dependable roofing equipment available. Table of Contents Featured Products.. 7 Sievert Safety.. 8 - 9 Sievert Turboroofer Torch Kits. 10 Sievert Turboroofer Multi-Piece Torch Kits.. 11 Sievert Turboroofer Torch Kit Accessories. 12 Sievert Promatic Torches and Kits.. 13 Sievert Promatic Repair Kits. .. 14 Sievert Promatic Torch Kit Accessories . .15 Sievert Granule Embedders, Sievert Industrial Steel Roller and Sievert Quality Hand Irons . .16 Sievert ES Soldering Iron Kits. 17 Sievert SIK Premium Soldering Iron Kits.. 18 Sievert LSK Premium Basic Soldering Iron Kits.. .19 Sievert ES, SIK and LSK Soldering Iron Kit Accessories.. .20 Sievert Heavy Duty Electronic Hot Air Guns and Accessories. .21 Sievert TW 5000 Hot-Air Automatic Welding Machine and Accessories. -
What Are Health Risks from Ionising Radiation?
What are health risks from Ionising Radiation? It has been known for many years that large doses of ionising radiation, very every 100 persons exposed to a short-term dose of 1000 mSv (ie. if the much larger than background levels, can cause a measurable increase in normal incidence of fatal cancer were 25%, this dose would increase it to cancers and leukemias (‘cancer of the blood’) after some years delay. It must 30%).If doses greater than 1000 mSv occur over a long period they are also be assumed, because of experiments on plants and animals, that ionising less likely to have early health effects but they create a definite risk that radiation can also cause genetic mutations that affect future generations, cancer will develop many years later. although there has been no evidence of radiation-induced mutation in Higher accumulated doses of radiation might produce a cancer which humans. At very high levels, radiation can cause sickness and death within would only be observed several – up to twenty – years after the radiation weeks of exposure. exposure. This delay makes it impossible to say with any certainty which The degree of damage caused by radiation depends on many factors – of many possible agents were the cause of a particular cancer. In western dose, dose rate, type of radiation, the part of the body exposed, age and countries, about a quarter of people die from cancers, with smoking, health, for example. Embryos including the human fetus are particularly dietary factors, genetic factors and strong sunlight being among the sensitive to radiation damage. -
International Basic Safety Standards for Protection Against Ionizing Radiation and for the Safety of Radiation Sources Safety5 Serie11
CATEGORIES IN THE IAEA SAFETY SERIES A hierarchical categorization scheme beenhas introduced, according whichto publicationsthe IAEAthe in Safety Series groupedare follows:as Safety Fundamentals (silver cover) Basic objectives, concepts and principles to ensure safety. Safety Standards (red cover) Basic requirements which mus e satisfieb t o ensurdt e safet r particulafo y r activitie r applicatioso n areas. Safety Guides (green cover) Recommendations, on the basis of international experience, relating to the fulfilmen f basio t c requirements. Safety Practices (blue cover) Practical example detailed san d method applicatioe s useth whice b r dn fo hca n of Safety Standards or Safety Guides. Safety Fundamentals and Safety Standards are issued with the approval of the IAEA Board of Governors; Safety Guides and Safety Practices are issued under the authorit Directoe th f yo r Genera IAEAe th f o l. Ther othee ear r IAEA publications which also contain information importano t safety, in particular in the Proceedings Series (papers presented at symposia and conferences) Technicae th , l Reports Series (emphasi technologican so l aspectsd an ) the IAEA-TECDOC Series (information usually in preliminary form). CORRIGENDA to International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources Safety5 Serie11 . sNo p. 48 In para 14(b. II . ) replace "focal spot position" with "focal spot size", p. 88 followine footnotn I th d Tablo pareno t ad ea I gtw e I- t nuclide progend san y (firs sixth)d an t : Sr-80 Rb-80 Ag-108m Ag-108 p. 91 In para. -
Internal and External Exposure Exposure Routes 2.1
Exposure Routes Internal and External Exposure Exposure Routes 2.1 External exposure Internal exposure Body surface From outer space contamination and the sun Inhalation Suspended matters Food and drink consumption From a radiation Lungs generator Radio‐ pharmaceuticals Wound Buildings Ground Radiation coming from outside the body Radiation emitted within the body Radioactive The body is equally exposed to radiation in both cases. materials "Radiation exposure" refers to the situation where the body is in the presence of radiation. There are two types of radiation exposure, "internal exposure" and "external exposure." External exposure means to receive radiation that comes from radioactive materials existing on the ground, suspended in the air, or attached to clothes or the surface of the body (p.25 of Vol. 1, "External Exposure and Skin"). Conversely, internal exposure is caused (i) when a person has a meal and takes in radioactive materials in the food or drink (ingestion); (ii) when a person breathes in radioactive materials in the air (inhalation); (iii) when radioactive materials are absorbed through the skin (percutaneous absorption); (iv) when radioactive materials enter the body from a wound (wound contamination); and (v) when radiopharmaceuticals containing radioactive materials are administered for the purpose of medical treatment. Once radioactive materials enter the body, the body will continue to be exposed to radiation until the radioactive materials are excreted in the urine or feces (biological half-life) or as the radioactivity weakens over time (p.26 of Vol. 1, "Internal Exposure"). The difference between internal exposure and external exposure lies in whether the source that emits radiation is inside or outside the body.