Chapter 3 Radiation Protection
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The American Postdramatic Television Series: the Art of Poetry and the Composition of Chaos (How to Understand the Script of the Best American Television Series)”
RLCS, Revista Latina de Comunicación Social, 72 – Pages 500 to 520 Funded Research | DOI: 10.4185/RLCS, 72-2017-1176| ISSN 1138-5820 | Year 2017 How to cite this article in bibliographies / References MA Orosa, M López-Golán , C Márquez-Domínguez, YT Ramos-Gil (2017): “The American postdramatic television series: the art of poetry and the composition of chaos (How to understand the script of the best American television series)”. Revista Latina de Comunicación Social, 72, pp. 500 to 520. http://www.revistalatinacs.org/072paper/1176/26en.html DOI: 10.4185/RLCS-2017-1176 The American postdramatic television series: the art of poetry and the composition of chaos How to understand the script of the best American television series Miguel Ángel Orosa [CV] [ ORCID] [ GS] Professor at the School of Social Communication. Pontificia Universidad Católica del Ecuador (Sede Ibarra, Ecuador) – [email protected] Mónica López Golán [CV] [ ORCID] [ GS] Professor at the School of Social Communication. Pontificia Universidad Católica del Ecuador (Sede Ibarra, Ecuador) – moLó[email protected] Carmelo Márquez-Domínguez [CV] [ ORCID] [ GS] Professor at the School of Social Communication. Pontificia Universidad Católica del Ecuador Sede Ibarra, Ecuador) – camarquez @pucesi.edu.ec Yalitza Therly Ramos Gil [CV] [ ORCID] [ GS] Professor at the School of Social Communication. Pontificia Universidad Católica del Ecuador (Sede Ibarra, Ecuador) – [email protected] Abstract Introduction: The magnitude of the (post)dramatic changes that have been taking place in American audiovisual fiction only happen every several hundred years. The goal of this research work is to highlight the features of the change occurring within the organisational (post)dramatic realm of American serial television. -
Section 1: Introduction (PDF)
SECTION 1: Introduction SECTION 1: INTRODUCTION Section 1 Contents The Purpose and Scope of This Guidance ....................................................................1-1 Relationship to CZARA Guidance ....................................................................................1-2 National Water Quality Inventory .....................................................................................1-3 What is Nonpoint Source Pollution? ...............................................................................1-4 Watershed Approach to Nonpoint Source Pollution Control .......................................1-5 Programs to Control Nonpoint Source Pollution...........................................................1-7 National Nonpoint Source Pollution Control Program .............................................1-7 Storm Water Permit Program .......................................................................................1-8 Coastal Nonpoint Pollution Control Program ............................................................1-8 Clean Vessel Act Pumpout Grant Program ................................................................1-9 International Convention for the Prevention of Pollution from Ships (MARPOL)...................................................................................................1-9 Oil Pollution Act (OPA) and Regulation ....................................................................1-10 Sources of Further Information .....................................................................................1-10 -
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 -
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. -
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. -
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. -
Sources and Emissions of Air Pollutants
© Jones & Bartlett Learning, LLC. NOT FOR SALE OR DISTRIBUTION Chapter 2 Sources and Emissions of Air Pollutants LEArning ObjECtivES By the end of this chapter the reader will be able to: • distinguish the “troposphere” from the “stratosphere” • define “polluted air” in relation to various scientific disciplines • describe “anthropogenic” sources of air pollutants and distinguish them from “natural” sources • list 10 sources of indoor air contaminants • identify three meteorological factors that affect the dispersal of air pollutants ChAPtEr OutLinE I. Introduction II. Measurement Basics III. Unpolluted vs. Polluted Air IV. Air Pollutant Sources and Their Emissions V. Pollutant Transport VI. Summary of Major Points VII. Quiz and Problems VIII. Discussion Topics References and Recommended Reading 21 2 N D R E V I S E 9955 © Jones & Bartlett Learning, LLC. NOT FOR SALE OR DISTRIBUTION 22 Chapter 2 SourCeS and EmiSSionS of Air PollutantS i. IntrOduCtiOn level. Mt. Everest is thus a minute bump on the globe that adds only 0.06 percent to the Earth’s diameter. Structure of the Earth’s Atmosphere The Earth’s atmosphere consists of several defined layers (Figure 2–1). The troposphere, in which all life The Earth, along with Mercury, Venus, and Mars, is exists, and from which we breathe, reaches an altitude of a terrestrial (as opposed to gaseous) planet with a per- about 7–8 km at the poles to just over 13 km at the equa- manent atmosphere. The Earth is an oblate (slightly tor: the mean thickness being 9.1 km (5.7 miles). Thus, flattened) sphere with a mean diameter of 12,700 km the troposphere represents a very thin cover over the (about 8,000 statute miles). -
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 ..................................................................... -
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. -
Expected Inflation and the Constant-Growth Valuation Model* by Michael Bradley, Duke University, and Gregg A
VOLUME 20 | NUMBER 2 | SPRING 2008 Journal of APPLIED CORPORATE FINANCE A MORGAN STANLEY PUBLICATION In This Issue: Valuation and Corporate Portfolio Management Corporate Portfolio Management Roundtable 8 Panelists: Robert Bruner, University of Virginia; Robert Pozen, Presented by Ernst & Young MFS Investment Management; Anne Madden, Honeywell International; Aileen Stockburger, Johnson & Johnson; Forbes Alexander, Jabil Circuit; Steve Munger and Don Chew, Morgan Stanley. Moderated by Jeff Greene, Ernst & Young Liquidity, the Value of the Firm, and Corporate Finance 32 Yakov Amihud, New York University, and Haim Mendelson, Stanford University Real Asset Valuation: A Back-to-Basics Approach 46 David Laughton, University of Alberta; Raul Guerrero, Asymmetric Strategy LLC; and Donald Lessard, MIT Sloan School of Management Expected Inflation and the Constant-Growth Valuation Model 66 Michael Bradley, Duke University, and Gregg Jarrell, University of Rochester Single vs. Multiple Discount Rates: How to Limit “Influence Costs” 79 John Martin, Baylor University, and Sheridan Titman, in the Capital Allocation Process University of Texas at Austin The Era of Cross-Border M&A: How Current Market Dynamics are 84 Marc Zenner, Matt Matthews, Jeff Marks, and Changing the M&A Landscape Nishant Mago, J.P. Morgan Chase & Co. Transfer Pricing for Corporate Treasury in the Multinational Enterprise 97 Stephen L. Curtis, Ernst & Young The Equity Market Risk Premium and Valuation of Overseas Investments 113 Luc Soenen,Universidad Catolica del Peru, and Robert Johnson, University of San Diego Stock Option Expensing: The Role of Corporate Governance 122 Sanjay Deshmukh, Keith M. Howe, and Carl Luft, DePaul University Real Options Valuation: A Case Study of an E-commerce Company 129 Rocío Sáenz-Diez, Universidad Pontificia Comillas de Madrid, Ricardo Gimeno, Banco de España, and Carlos de Abajo, Morgan Stanley Expected Inflation and the Constant-Growth Valuation Model* by Michael Bradley, Duke University, and Gregg A. -
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.