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The Utilization of MOSFET Dosimeters for Clinical Measurements in Radiology
The Utilization of MOSFET Dosimeters for Clinical Measurements in Radiology David Hintenlang, Ph.D., DABR, FACMP Medical Physics Program Director J. Crayton Pruitt Family Department of Biomedical Engineering J. Crayton Pruitt Family Department of Biomedical Engineering Medical Physics Program Conflict of interest statement: The presenter holds no financial interest in, and has no affiliation or research support from any manufacturer or distributor of MOSFET Dosimetry systems. J. Crayton Pruitt Family Department of Biomedical Engineering Medical Physics Program The MOSFET Dosimeter • Metal oxide silicon field effect transistor • Uniquely packaged to serve as a radiation detector – developed as early as 1974 • Applications – Radiation Therapy Dose Verification – Cosmic dose monitoring on satellites – Radiology • ~ 1998 - present J. Crayton Pruitt Family Department of Biomedical Engineering Medical Physics Program Attractive features • Purely electronic dosimeter • Provides immediate dose feedback • Integrates over short periods of time • Small size and portability • Simultaneous measurements (up to 20) J. Crayton Pruitt Family Department of Biomedical Engineering Medical Physics Program Demonstrated radiology applications – Patient dose monitoring/evaluation • Radiography • Fluoroscopic and interventional procedures • CT • Mammography J. Crayton Pruitt Family Department of Biomedical Engineering Medical Physics Program Principles of operation • Ionizing radiation results in the creation of electron-hole pairs • Holes migrate and build up -
RADIATION EFFECTS and SOURCES What Is Radiation? What Does Radiation Do to Us? Where Does Radiation Come From?
RADIATION EFFECTS and SOURCES What is radiation? What does radiation do to us? Where does radiation come from? United Nations Environment Programme RADIATION EFFECTS and SOURCES What is radiation? What does radiation do to us? Where does radiation come from? United Nations Environment Programme DISCLAIMER This publication is largely based on the findings of the United Nations Scientific Committee on the Effects of Atomic Radiation, a subsidiary body of the United Nations General Assembly and for which the United Nations Environment Pro- gramme provides the secretariat. This publication does not necessarily r epresent the views of the Scientific Committee or of the United Nations Environment Programme. The designations employed and the presentation of the material in this publica- tion do not imply the expression of any opinion whatsoever on the part of the United Nations Environment Programme concerning the legal status of any country, territory, city or area or of its authorities, or concerning delimitation of its frontiers or boundaries. This publication may be reproduced in whole or in part and in any form for educational or non-profit purposes without special permission from the copyright holder, provided acknowledgement of the source is made. The United Nations Environment Programme would appreciate receiving a copy of any publication that uses this publication as a source. No use of this publication may be made for resale or for any other commercial purpose whatsoever without prior permission in writing from the United Nations Environment Programme. The United Nations Environment Programme promotes environmentally sound practices globally and in its own activities. This publication was printed on recycled paper, 100 per cent chlorine free. -
CNS Ionising Radiation Workshop Notes
Ionising Radiation Workshop Page 1 of 82 Canadian Nuclear Society Ionising Radiation Workshop Be Aware of NORM CNS Team Bryan White Doug De La Matter Peter Lang Jeremy Whitlock First presented concurrently at: The Science Teachers’ Association of Ontario Annual Conference, Toronto; and The Alberta Teachers’ Association Science Council Conference, Calgary 2008 November 14 Revision 12 Presentation at: Association of Science Teachers Provincial Conference 2013 Halifax NS October 25th, 2013 Ionising Radiation Workshop Page 2 of 82 Revision History Revision 1: 2008-11-06 (Note revisions modify page numbers) Page Errata 10 Last paragraph: “…emit particles containing (only) two protons …” (add parentheses) 11 Table, Atomic No. 86, 1st radon mass number should be 220. 20 Insert section 3.4 Shielding – affects page numbers 24 1st paragraph: “…with the use of shielding absorbers.” (insert “shielding”) 26 1st paragraph: “… of consistent data can be time consuming.” (delete “it”) 32 List item 6, last sentence: “The container contents have an activity of about 5 kBq.” (emphasis on contents) 44 2nd paragraph, 4th sentence: “… surface exposure of 360 µSv to 8.8 mSv …” (µSv not mSv) 45 2nd paragraph, 2nd sentence: “ … radioactivity compared to thorium ore …” (delete “the”) 47 2nd paragraph: “Because the lens diameter is not much smaller …” (insert “not”) Revision 2: 2009-02-04 5 Deleted 2 pages re CNA website S 3.2 Discussion of radon decay and health hazard inserted 38 Experiment 3, Part I – results from a more extensive absorber experiment show that the alpha radiation scatters electrons from the foils with energy higher than the beta from the thorium decay chain 51 Appendix C (now D): Note added that more recent “non-divide-by-two” modules are also red in colour. -
Rulemaking for Enhanced Security of Special Nuclear Material
Rulemaking for Enhanced Security of Special Nuclear Material RIN number: 3150-AJ41 NRC Docket ID: NRC-2014-0118 Regulatory Basis Document January 2015 Table of Contents 1. Introduction and Background .............................................................................................. 1 2. Existing Regulatory Framework .......................................................................................... 3 2.1 Regulatory History ............................................................................................................. 3 2.2 Existing Regulatory Requirements .................................................................................... 8 3. Regulatory Problem .......................................................................................................... 13 3.1 Generic Applicability of Security Orders .......................................................................... 13 3.2 Risk Insights .................................................................................................................... 16 3.3 Consistency and Clarity .................................................................................................. 27 3.4 Use of a Risk-Informed and Performance-Based Structure. ........................................... 29 4. Basis for Requested Changes ........................................................................................... 30 4.1 Material Categorization and Attractiveness ..................................................................... 30 4.2 -
Basics of Radiation Radiation Safety Orientation Open Source Booklet 1 (June 1, 2018)
Basics of Radiation Radiation Safety Orientation Open Source Booklet 1 (June 1, 2018) Before working with radioactive material, it is helpful to recall… Radiation is energy released from a source. • Light is a familiar example of energy traveling some distance from its source. We understand that a light bulb can remain in one place and the light can move toward us to be detected by our eyes. • The Electromagnetic Spectrum is the entire range of wavelengths or frequencies of electromagnetic radiation extending from gamma rays to the longest radio waves and includes visible light. Radioactive materials release energy with enough power to cause ionizations and are on the high end of the electromagnetic spectrum. • Although our bodies cannot sense ionizing radiation, it is helpful to think ionizing radiation behaves similarly to light. o Travels in straight lines with decreasing intensity farther away from the source o May be reflected off certain surfaces (but not all) o Absorbed when interacting with materials You will be using radioactive material that releases energy in the form of ionizing radiation. Knowing about the basics of radiation will help you understand how to work safely with radioactive material. What is “ionizing radiation”? • Ionizing radiation is energy with enough power to remove tightly bound electrons from the orbit of an atom, causing the atom to become charged or ionized. • The charged atoms can damage the internal structures of living cells. The material near the charged atom absorbs the energy causing chemical bonds to break. Are all radioactive materials the same? No, not all radioactive materials are the same. -
Radiation Safety Evidence Table
Guideline for Radiation Safety Evidence Table Citation Conclusion(s) Evidence Type Population Reference# Sample Sample size Intervention Comparision Concensus Concensus score Outcome measure Outcome 1 Chaffins JA. Radiation protection and procedures in Describes radiation protection Expert oninion VB N/A N/A N/A N/A N/A the OR. Radiol Technol . 2008;79(5): 415-428. measures and procedures for radiation protection in the OR. 2 Bindal RK, Glaze S, Ognoskie M, Tunner V, Malone The amount of radiation received by Descriptive IIIC 1 surgeon, N/A N/A 1 surgeon, 24 Radiaiton dose R, Ghosh S. Surgeon and patient radiation patients and physicians is low during 24 patients patients exposure in minimally invasive transforaminal minimally invasive transforaminal lumbar interbody fusion. J Neurosurg Spine. lumbar interbody fusion. 2008;9(6):570–573. 3 Cattani F, Vavassori A, Polo Aet al. Radiation A visitor should stay 1 meter away Descriptive, IIIC Patients N/A N/A 216 patients Radiation dose exposure after permanent prostate brachytherapy. from the patient who has radioactive retrospective Radiother Oncol. 2006;79(1):65–69. seeds implanted for a period of time equal to the half life of the radionuclide to achieve a radiation does as low as reasonably/readily achievable. 4 Brown KR, Rzucidlo E. Acute and chronic radiation Suggestions for patient education and Literature review VB N/A N/A N/A N/A N/A injury. J Vasc Surg. 2011;53(1 Suppl):15S–21S. tips to avoid injury, description of injuries from radiation, patient risk factors for injury. 5 Miller DL. Efforts to optimize radiation protection Historical review of all aspects of Literature review VA N/A N/A N/A N/A N/A in interventional fluoroscopy. -
NATO and NATO-Russia Nuclear Terms and Definitions
NATO/RUSSIA UNCLASSIFIED PART 1 PART 1 Nuclear Terms and Definitions in English APPENDIX 1 NATO and NATO-Russia Nuclear Terms and Definitions APPENDIX 2 Non-NATO Nuclear Terms and Definitions APPENDIX 3 Definitions of Nuclear Forces NATO/RUSSIA UNCLASSIFIED 1-1 2007 NATO/RUSSIA UNCLASSIFIED PART 1 NATO and NATO-Russia Nuclear Terms and Definitions APPENDIX 1 Source References: AAP-6 : NATO Glossary of Terms and Definitions AAP-21 : NATO Glossary of NBC Terms and Definitions CP&MT : NATO-Russia Glossary of Contemporary Political and Military Terms A active decontamination alpha particle A nuclear particle emitted by heavy radionuclides in the process of The employment of chemical, biological or mechanical processes decay. Alpha particles have a range of a few centimetres in air and to remove or neutralise chemical, biological or radioactive will not penetrate clothing or the unbroken skin but inhalation or materials. (AAP-21). ingestion will result in an enduring hazard to health (AAP-21). décontamination active активное обеззараживание particule alpha альфа-частицы active material antimissile system Material, such as plutonium and certain isotopes of uranium, The basic armament of missile defence systems, designed to which is capable of supporting a fission chain reaction (AAP-6). destroy ballistic and cruise missiles and their warheads. It includes See also fissile material. antimissile missiles, launchers, automated detection and matière fissile радиоактивное вещество identification, antimissile missile tracking and guidance, and main command posts with a range of computer and communications acute radiation dose equipment. They can be subdivided into short, medium and long- The total ionising radiation dose received at one time and over a range missile defence systems (CP&MT). -
Re-Examining the Role of Nuclear Fusion in a Renewables-Based Energy Mix
Re-examining the Role of Nuclear Fusion in a Renewables-Based Energy Mix T. E. G. Nicholasa,∗, T. P. Davisb, F. Federicia, J. E. Lelandc, B. S. Patela, C. Vincentd, S. H. Warda a York Plasma Institute, Department of Physics, University of York, Heslington, York YO10 5DD, UK b Department of Materials, University of Oxford, Parks Road, Oxford, OX1 3PH c Department of Electrical Engineering and Electronics, University of Liverpool, Liverpool, L69 3GJ, UK d Centre for Advanced Instrumentation, Department of Physics, Durham University, Durham DH1 3LS, UK Abstract Fusion energy is often regarded as a long-term solution to the world's energy needs. However, even after solving the critical research challenges, engineer- ing and materials science will still impose significant constraints on the char- acteristics of a fusion power plant. Meanwhile, the global energy grid must transition to low-carbon sources by 2050 to prevent the worst effects of climate change. We review three factors affecting fusion's future trajectory: (1) the sig- nificant drop in the price of renewable energy, (2) the intermittency of renewable sources and implications for future energy grids, and (3) the recent proposition of intermediate-level nuclear waste as a product of fusion. Within the scenario assumed by our premises, we find that while there remains a clear motivation to develop fusion power plants, this motivation is likely weakened by the time they become available. We also conclude that most current fusion reactor designs do not take these factors into account and, to increase market penetration, fu- sion research should consider relaxed nuclear waste design criteria, raw material availability constraints and load-following designs with pulsed operation. -
Nuclear Regulatory Commission § 70.5
Nuclear Regulatory Commission § 70.5 section 51 of the act, determines to be intermediates, which are unsuitable for special nuclear material, but does not use in their present form, but all or include source material; or (2) any ma- part of which will be used after further terial artificially enriched by any of processing. the foregoing but does not include Strategic special nuclear material source material; means uranium-235 (contained in ura- Special nuclear material of low strategic nium enriched to 20 percent or more in significance means: the U235 isotope), uranium-233, or pluto- (1) Less than an amount of special nium. nuclear material of moderate strategic Transient shipment means a shipment significance as defined in paragraph (1) of nuclear material, originating and of the definition of strategic nuclear terminating in foreign countries, on a material of moderate strategic signifi- vessel or aircraft which stops at a cance in this section, but more than 15 United States port. grams of uranium-235 (contained in Unacceptable performance deficiencies uranium enriched to 20 percent or more mean deficiencies in the items relied in U-235 isotope) or 15 grams of ura- on for safety or the management meas- nium-233 or 15 grams of plutonium or ures that need to be corrected to en- the combination of 15 grams when com- sure an adequate level of protection as puted by the equation, grams = (grams defined in 10 CFR 70.61(b), (c), or (d). contained U-235) + (grams plutonium) + United States, when used in a geo- (grams U-233); or graphical sense, includes Puerto Rico (2) Less than 10,000 grams but more and all territories and possessions of than 1,000 grams of uranium-235 (con- the United States. -
Shielding for Radiation Scattered Dose Distribution to the Outside Fields in Patients Treated with High Energy Radiotherapy Beams
IAEA-CN-85-70 SHIELDING FOR RADIATION SCATTERED DOSE DISTRIBUTION TO THE OUTSIDE FIELDS IN PATIENTS TREATED WITH HIGH ENERGY RADIOTHERAPY BEAMS SungSilChu XA0101718 Department of radiation Oncology, Yonsei Cancer Center, Yonsei University, Seoul, Republic of Korea Abstract Scattered dose of therapeutic high energy radiation beams are contributed significan t unwanted dose to the patient. Measurement of radiation scattered dose outside fields and critical organs, like fetus position and testicle region, from chest or pelvic irradiation by large field of high energy radiation beam was performed using an ionization chamber and film dosimetry. The scattered doses outside field were measured 5 - 10% of maximum doses in fields and exponentially decrease from field margins. The scattered photon dose received the uterus from thorax field irradiation was measured about lmGy/Gy of photon treatment dose Shielding construction to reduce this scattered dose was investigated using lead sheet and blocks About 6 cm lead block shield reduced the scatter photon dose under lOmGy for 60Gy on abdomen field and reduced almost electron contamination. 1. Introduction High energy photon beams from medical linear accelerators produce large scattered radiation by various components of the treatment head, collimator and walls or objects in the treatment room including the patient. These scattered radiation do not provide therapeutic dose and are considered a hazard from the radiation safety perspective. The scattered photon dose received the fetus from thorax field irradiation was measured about lmGy/Gy of photon treatment dose and typical therapeutic doses of photon radiation lie in the range 40 -70Gy. Thus, without additional shielding, the scattered photon dose received by the fetus might be several hundred mGy. -
Experiment "Gamma Dosimetry and Dose Rate Determination" Instruction for Experiment "Gamma Dosimetry and Dose Rate Determination"
TECHNICAL UNIVERSITY DRESDEN Institute of Power Engineering Training Reactor Reactor Training Course Experiment "Gamma Dosimetry and Dose Rate Determination" Instruction for Experiment "Gamma Dosimetry and Dose Rate Determination" Content: 1 .... Motivation 2..... Theoretical Background 2.1... Properties of Ionising Radiation and Interactions of Gamma Radiation 2.2. Detection of Ionising Radiation 2.3. Quantities and Units of Dosimetry 3..... Procedure of the Experiment 3.1. Commissioning and Calibration of the Dosimeter Thermo FH40G 3.2. Commissioning and Calibration of the Dosimeter Berthold LB 133-1 3.3. Commissioning and Calibration of the Dosimeter STEP RGD 27091 3.4. Setup of the Experiment 3.4.1. Measurement of Dose Rate in Various Distances from the Radiation Source 3.4.2. Measurement of Dose Rate behind Radiation Shielding 3.5. Measurement of Dose Rate at the open Reactor Channel 4..... Evaluation of Measuring Results Figures: Fig. 1: Composition of the attenuation coefficient µ of γ-radiation in lead Fig. 2: Design of an ionisation chamber Fig. 3: Classification and legal limit values of radiation protection areas Fig. 4: Setup of the experiment (issued: January 2019) - 1 - 1. Motivation The experiment aims on familiarising with the methods of calibrating different detectors for determination of the dose and the dose rate. Furthermore, the dose rate and the activity in the vicinity of an enclosed source of ionising radiation (Cs-137) will be determined taking into account the background radiation and the measurement accuracy. Additionally, the experiment focuses on the determination of the dose rate of a shielded source as well as on the calculation of the required thickness of the shielding protection layer for meeting the permissible maximum dose rate. -
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.