INTRODUCTION This Training Manual Presents a Knowledge Base Extracted from 10CFR's, the MURSOM, NRC Regulatory Guides and the Li
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Dead Time and Count Loss Determination for Radiation Detection Systems in High Count Rate Applications
Scholars' Mine Doctoral Dissertations Student Theses and Dissertations Spring 2010 Dead time and count loss determination for radiation detection systems in high count rate applications Amol Patil Follow this and additional works at: https://scholarsmine.mst.edu/doctoral_dissertations Part of the Nuclear Engineering Commons Department: Nuclear Engineering and Radiation Science Recommended Citation Patil, Amol, "Dead time and count loss determination for radiation detection systems in high count rate applications" (2010). Doctoral Dissertations. 2148. https://scholarsmine.mst.edu/doctoral_dissertations/2148 This thesis is brought to you by Scholars' Mine, a service of the Missouri S&T Library and Learning Resources. This work is protected by U. S. Copyright Law. Unauthorized use including reproduction for redistribution requires the permission of the copyright holder. For more information, please contact [email protected]. DEAD TIME AND COUNT LOSS DETERMINATION FOR RADIATION DETECTION SYSTEMS IN HIGH COUNT RATE APPLICATIONS by AMOL PATIL A DISSERTATION Presented to the Faculty of the Graduate School of the MISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY In Partial Fulfillment of the Requirements for the Degree DOCTOR OF PHILOSOPHY in NUCLEAR ENGINEERING 2010 Approved by Shoaib Usman, Advisor Arvind Kumar Gary E. Mueller Carlos H. Castano Bijaya J. Shrestha © 2010 AMOL PATIL All Rights Reserved iii PUBLICATION DISSERTATION OPTION This dissertation consists of the following two articles that have been, or will be submitted for publication as follows: Pages 4-40 are intended for submission to Journal of Radioanalytical and Nuclear Chemistry. Pages 41-62 have been published in Nuclear Technologies journal (February, 2009). iv ABSTRACT This research is focused on dead time and the subsequent count loss estimation in radiation detection systems. -
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). -
Optimization of a Gas Flow Proportional Counter for Alpha Decay
Optimization of a gas flow proportional counter for alpha decay measurements Elena Ceballos Romero Master Thesis Institut f¨urKernphysik Mathematisch-Naturwissenschaftliche Fakult¨at Westf¨alische Wilhelms-Universit¨atM¨unster Prof. Dr. Alfons Khoukaz October 2012 III I am among those who think that science has great beauty. A scientist in his laboratory is not only a technician: he is also a child placed before natural phenomena which impress him like a fairy tale. We should not allow it to be believed that all scientific progress can be reduced to mechanisms, machines, gearings, even though such machinery has its own beauty. -Marie Curie A magdalena, por ponerme en este camino. A mis padres, por siempre acompa~narmeen ´el. IV V I certify that I have independently written this thesis and no other sources than the mentioned ones have been used. Referent: Prof. Dr. Alfons Khoukaz Correferent: Dr. Mar´ıaVilla Alfageme VI Contents 1. Introduction 1 2. Introduction to natural radiations 5 2.1. Radioactivity . .5 2.1.1. Decay laws . .5 2.1.2. Activity . .7 2.2. Decays . .7 2.2.1. Alpha decay . .7 2.2.2. Beta decay . .9 2.2.3. Gamma decay . 11 3. Theoretical background: Gas-filled detectors 13 3.1. General properties . 13 3.1.1. Number of ion pairs formed . 14 3.1.2. Behaviour of charged particles in gases . 14 3.1.3. Operational modes of gas detectors . 15 3.2. Proportional counters: gas multiplication effect . 17 3.3. Gas flow detectors . 18 4. Experimental set-up 21 4.1. Detector . 21 4.1.1. -
Radiation Glossary
Radiation Glossary Activity The rate of disintegration (transformation) or decay of radioactive material. The units of activity are Curie (Ci) and the Becquerel (Bq). Agreement State Any state with which the U.S. Nuclear Regulatory Commission has entered into an effective agreement under subsection 274b. of the Atomic Energy Act of 1954, as amended. Under the agreement, the state regulates the use of by-product, source, and small quantities of special nuclear material within said state. Airborne Radioactive Material Radioactive material dispersed in the air in the form of dusts, fumes, particulates, mists, vapors, or gases. ALARA Acronym for "As Low As Reasonably Achievable". Making every reasonable effort to maintain exposures to ionizing radiation as far below the dose limits as practical, consistent with the purpose for which the licensed activity is undertaken. It takes into account the state of technology, the economics of improvements in relation to state of technology, the economics of improvements in relation to benefits to the public health and safety, societal and socioeconomic considerations, and in relation to utilization of radioactive materials and licensed materials in the public interest. Alpha Particle A positively charged particle ejected spontaneously from the nuclei of some radioactive elements. It is identical to a helium nucleus, with a mass number of 4 and a charge of +2. Annual Limit on Intake (ALI) Annual intake of a given radionuclide by "Reference Man" which would result in either a committed effective dose equivalent of 5 rems or a committed dose equivalent of 50 rems to an organ or tissue. Attenuation The process by which radiation is reduced in intensity when passing through some material. -
ACUTE RADIATION SYNDROME: Diagnosis and Treatment
ACUTE RADIATION SYNDROME: Diagnosis and Treatment Badria Al Hatali, MD Medical Toxicologist Department of Environmental and Occupational Health MOH - Oman Objectives Provide a review of radiation basics and acute radiation sickness Discuss diagnostic tools and triage tools for Acute Radiation Syndromes Discuss management of Acute Radiation Syndromes Energy traveling over a distance as Waves Particles • Gamma rays • Alpha • X-rays • Beta • Radio waves • neurons Non-ionizing vs Ionizing Radiation • High energy • Low energy • Removes orbital electrons • Does not remove orbital from atoms > DNA electrons from atom damage Radioactive Decay Process to Remove excess energy from atomic nuclei Nuclei emit rays or particles to decrease nuclear energy Radioactive materials have unstable nuclei with excess energy Ionizing Radiation Dose • Radiation absorb dose (RAD): the amount of energy absorbed by the body. 1 cGy = 0.01 J/kg (USA) • Gray (Gy): expressed as absorbed energy per unit mass of tissue. 100 rad =100 cGy =1 J/kg (SI) • Roentgen Equivalent Man (REM) relates the absorbed dose in human tissue to the effective biological damage of the radiation (USA) • Sievert (Sv): the absorbed dose in human tissue to the effective biological damage of the radiation (SI) Radioactivity Biological And Effective Half-lives Biological half-life is the time to remove half of radioactive element from body Effective half-life is the combined effect of radioactive decay & biological elimination Effective half-life is always shorter than either physical or biological half-lives Biological Effects of Ionizing Radiation Direct damage Chromosome Other biochemical E.g. alpha and beta particles Indirect damage Chemical changes due to radiolysis of water in cell E.g. -
Radiation Fields Using a Tepc*
XA00XC014 EUROPEAN LABORATORY FOR PARTICLE PHYSICS CERN/TIS-RP/95-14/CF A STUDY OF BUILD-UP EFFECTS IN HIGH-ENERGY RADIATION FIELDS USING A TEPC* M. Hofert1), A. Aroua2), A. V. Sannikov3) and G. R. Stevenson1) !) CERN, European Laboratory for Particle Physics, CH 1211 Geneva 23, Switzerland 2) IAR, Institute for Applied Radiophysics, CH 1015 Lausanne, Switzerland 3) IHEP, Institute for High-Energy Physics, RU 142284 Protvino, Russia * Supported by EU Research Contract FI3P-CT92-0026 Abstract A dose of 2 mSv close to the body surface of a pregnant woman is considered by ICRP to assure a dose limit of 1 mSv to the foetus. Such an assumption depends on the energy spectrum and composition of the external radiation field and it was tested in radiation fields containing high-energy particles similar to those found around high-energy particle accelerators and in air-craft. Measurements of dose and dose equivalent were performed as a function of wall thickness using a tissue-equivalent proportional counter (TEPC) in radiation fields at the CERN-EU Reference Radiation Facility. Results are presented both with respect to integral quantities and event size spectra. The decrease in dose and dose equivalent at a depth equivalent to that of the foetus was typically 10% in a high-energy stray radiation field and in the case of Pu- Be source neutrons amounted to only 30%. It is concluded that it would be prudent under such exposure conditions to limit the dose of a pregnant woman to 1 mSv in order to assure that the dose to the foetus remains below the same limit. -
Ionizing Radiation in Earth's Atmosphere and in Space Near Earth May 2011 6
Federal Aviation Administration DOT/FAA/AM-11/9 Office of Aerospace Medicine Washington, DC 20591 Ionizing Radiation in Earth’s Atmosphere and in Space Near Earth Wallace Friedberg Kyle Copeland Civil Aerospace Medical Institute Federal Aviation Administration Oklahoma City, OK 73125 May 2011 Final Report OK-11-0024-JAH NOTICE This document is disseminated under the sponsorship of the U.S. Department of Transportation in the interest of information exchange. The United States Government assumes no liability for the contents thereof. ___________ This publication and all Office of Aerospace Medicine technical reports are available in full-text from the Civil Aerospace Medical Institute’s publications Web site: www.faa.gov/library/reports/medical/oamtechreports Technical Report Documentation Page 1. Report No. 2. Government Accession No. 3. Recipient's Catalog No. DOT/FAA/AM-11/9 4. Title and Subtitle 5. Report Date Ionizing Radiation in Earth's Atmosphere and in Space Near Earth May 2011 6. Performing Organization Code 7. Author(s) 8. Performing Organization Report No. Friedberg W, Copeland K 9. Performing Organization Name and Address 10. Work Unit No. (TRAIS) FAA Civil Aerospace Medical Institute P.O. Box 25082 11. Contract or Grant No. Oklahoma City, OK 73125 12. Sponsoring Agency name and Address 13. Type of Report and Period Covered Office of Aerospace Medicine Federal Aviation Administration 800 Independence Ave., S.W. Washington, DC 20591 14. Sponsoring Agency Code 15. Supplemental Notes 16. Abstract The Civil Aerospace Medical Institute of the FAA is charged with identifying health hazards in air travel and in commercial human space travel. -
Radiation Biology: Cell Biology
Agenda Radiologic Units: • Greys, Sieverts, Coulombs per kg, & What You Need to Becquerel's Know • Conventional Units TODD VAN AUKEN M.ED. RT (R)(MR) • Other Concepts (LET, Q-Factor, Effective Dose, NCRP Report # 116) • Crazy Happenings with Radiation Coulomb per kg or C/kg-Exposure (X) Erythema Dose • A Coulomb (C) is the basic unit of electric charge • Measurement of positive and negative particles created when radiation ionizes atoms in dry air (Radiation intensity in the air) • Unit of Exposure for X-rays and Gamma Rays (Restricted to Photons only) • Used for x-ray equipment calibration (X-ray tube output) • Conventional Unit: Roentgen (R) Air Kerma Gray (Gy)-Absorbed Dose (D) • Kinetic energy is transferred from the primary beam • Amount of energy per unit mass absorbed by an (photons) to the patient (e-) irradiated object • SI quantity that can be used to measure radiation • 1 joule (J) of energy absorbed concentration transferred to a point at the surface of a in 1 g of absorbing material patient’s or radiographer’s body • Absorption of energy may • The energy transfer is called the kinetic energy result in biological damage released in the material or kerma (air kerma) • As the Z# of the object • Dose Area Product (DAP)- sum total of Air Kerma increases the absorbed dose over the exposed area of the patient’s surface (entire increases amount of energy delivered to the patient) • Conventional Unit: RAD (Radiation Absorbed Dose) Linear Energy Transfer Linear Energy Transfer Low LET Low LET High LET High LET LET= Rate at which energy -
Q: What's the Difference Between Roentgen, Rad and Rem Radiation Measurements?
www.JICReadiness.com Q: What's the Difference Between Roentgen, Rad and Rem Radiation Measurements? A: Since nuclear radiation affects people, we must be able to measure its presence. We also need to relate the amount of radiation received by the body to its physiological effects. Two terms used to relate the amount of radiation received by the body are exposure and dose. When you are exposed to radiation, your body absorbs a dose of radiation. As in most measurement quantities, certain units are used to properly express the measurement. For radiation measurements they are... Roentgen: The roentgen measures the energy produced by gamma radiation in a cubic centimeter of air. It is usually abbreviated with the capital letter "R". A milliroentgen, or "mR", is equal to one one-thousandth of a roentgen. An exposure of 50 roentgens would be written "50 R". Rad: Or, Radiation Absorbed Dose recognizes that different materials that receive the same exposure may not absorb the same amount of energy. A rad measures the amount of radiation energy transferred to some mass of material, typically humans. One roentgen of gamma radiation exposure results in about one rad of absorbed dose. Rem: Or, Roentgen Equivalent Man is a unit that relates the dose of any radiation to the biological effect of that dose. To relate the absorbed dose of specific types of radiation to their biological effect, a "quality factor" must be multiplied by the dose in rad, which then shows the dose in rems. For gamma rays and beta particles, 1 rad of exposure results in 1 rem of dose. -
Note on Using Low-Sensitivity Geigers with The
Canadian Nuclear Society Working with less sensitive Geiger-Müeller Instruments www.cns-snc.ca Education Teachers … Page 1 of 4 Introduction The CNS Ionising Radiation Workshop features the use of higher sensitivity Geiger-Müeller detectors than most high school science teachers have access to. This note illustrates the impact of using lower sensitivity instruments with weak sources – AND shows how they may be used with the more intense sources described in the Workshop Notes. Damn lies and statistics The collection of count data with an instrument such as a Geiger detector is made using assumptions that are important to the analysis of the data set. These include: 1. Stable background radiation level 2. Consistent geometry 3. Stable sensitivity Lower sensitivity detectors have correspondingly lower average count rates when monitoring an ionising radiation source, including background radiation. Consequently it is difficult to detect the presence of ionising radiation sources that provide only a modest increase over the background rate. This limitation is due to the statistics of the count data. The pulses from a Geiger counter are collected as a number of counts in a time interval, for example the number of counts in a one minute interval. These are integer values. The average number of counts over a number of one-minute counting intervals is a real number. The one-minute interval data set may be described in terms of a Poisson probability distribution. For a data set with a large number of sample intervals and a sufficiently high average number per interval the probability distribution tends toward a Normal (or Gaussian) distribution. -
Gas Gain in Air-Mixed Argon-Propane (1%)-Based Proportional Counters
Gas Gain in Air-mixed Argon-Propane (1%)-based Proportional Counters D. Mazed♣ and R. Ciolini Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione, Università di Pisa Via Diotisalvi, 2, I-56126, Pisa, Italy. E-mail: [email protected] Abstract. For the design of a special gas-flow proportional counter intended for a new on-line measurement method of airborne radon (222Rn) concentration, the amplification properties of four gas compositions were investigated in air-mixed Argon-propane (1%)-based proportional counters. These four gas compositions are: Ar-C3H8 (1%); Ar-C3H8 (1%) + 2% air; Ar-C3H8 (1%) + 6% air and Ar-C3H8 (1%) + 10% air. The influence of the electron attachment effect due to oxygen on the saturation and gas amplification characteristics was examined in particular. The semi-microscopic gas gain formula was found to describe accurately the gas gain data obtained in each of the gas mixtures analyzed allowing the determination of the gas constants. The use of air-mixed counting gases in a specially designed gas-flow proportional counter for airborne radon concentration measurements appeared quite viable. 1. Introduction Being a radioactive noble gas, Radon (222Rn) presents some very particular properties: it diffuses easily out of soils or building materials and easily spreads out throughout the environment. Consequently, different concentrations of 222Rn and of its progenies can be found everywhere around us. Since it is an inert gas, 222Rn does not react chemically with other atoms or molecules. This makes its chemical trapping impossible and its physical trapping also difficult. Due to the importance of radon activity concentration for radiation protection, several detection systems and various measurement methods were developed in the past aiming at an accurate assessment of its concentration in air. -
Sludge Stabil: Hanford Site, Zation at the Plutonium Finish
DOE~A-0978 . Sludge Stabil:zation at the Plutonium Finish: ng Plant, -, Hanford Site, Mchland, Washington U.S. Dep-ent of Energ NcMand, Wash@on October 1994 _—_— DOE~A-0978 I I ( I —....— .—.. U,S. Deparment of Energy Glossary Glossary Acronp md Abbreviation ARF airborne release fraction ASIL Acceptable Source Impact Level D&D dmontamination and decommissioning DOE U.S. Department of Energy EA Environment Assessment Ecology State of Washington Department of Ecology EDE effective dose equivalent EIS Environment Impact Statement EPA U.S. Environment Protection Agency FFTF Fmt Flux Test Facflity HEPA High-Efficiency Partictiate Air LFL lower flammability limit LCF latent cancer fatrdity NESHAP Natioti Emission S~dards for H=dous Air Pollutants PFP Plutonium Finishing Plant PRF Plutonium Reclamation Factiity PUREX Plutonium-Uranium Extraction RCW Resource Conservationand Recove~ A~ of 1976 rem Roentgen Equivalent Man RMC ~ remote mechanical “C” TBP tributyl phosphate TLV-STEL Threshold Limit Value - Short Term Exposure Limit TLV-TWA Threshold Limit Value - Time Weighted Average Tri-Party Agreement Hanford Federal Facilip Agreement and Consent Order TRUS@ Transuranic Waste Storage and Assay Factiity WAC WmhingtonAdministr~.ve Code WIPP Waste Isolation Ptiot Plant Definition of Selected Tem Effective Dose Eauivdent. A value used for estimating the toti risk of potential health effects from radiation exposure. This estimate is the sum of the committed effective dose equivalent from interti deposition of radionuclidm in the body and the effective dose equivalent from exterti radiation received during a year. Latent cancer fatalitv: The excess mcer fatiities h a population due to exposure to a carcinogen. DOEEA-0978 October 1994 — -—— — U.S.