Radiation Weighting Factors
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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 ..................................................................... -
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. -
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. -
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). -
General Chapter <821> Radioactivity
BRIEFING 821 Radioactivity, USP 38 page 616. This chapter was introduced in its current form in 1975 and has not undergone any major revision since its first publication. Currently, ⟨the chapter⟩ contains definitions, special considerations, and procedures with respect to the monographs for radiopharmaceuticals (radioactive drugs). The majority of this chapter is informational. USP has launched an initiative to minimize nonprocedural information in general chapters with numbers below 1000. The USP Council of Experts believes that 821 should be revised as part of this initiative. To achieve this objective, several members of the USP Council of Experts jointly published a Stimuli article in PF 38(4) [July–Aug.⟨ 2012],⟩ Revision of General Chapter Radioactivity 821 . The objectives of this Stimuli article were threefold: (1) provide background information about the need for the proposed revision, (2) initiate discussion about this topic, and⟨ (3)⟩ solicit public comments for review and discussion by the relevant Expert Committee and Expert Panel members and USP staff. The current chapter is divided into two major sections, General Considerations and Identification and Assay of Radionuclides, both of which contain several subsections with information about aspects of radioactivity. Because of the nature of the information presented in these subsections, these can be moved to the proposed Radioactivity— Theory and Practice 1821 . The Terms and Definitions section is now listed as Glossary and has been revised to reflect current practices. The revised chapter will contain procedures and⟨ information⟩ about instrumentation used in the identification and assay of the radionuclides, along with appropriate information about calibration and maintenance of instrumentation. -
Overview and Basis of Design for NCRP Report
This Report was prepared through a joint effort of NCRP Scientific Committee 46-13 on Design of Facilities for Medical Radiation Overview & Basis of Design for NCRP Therapy and AAPM Task Group 57. Report 151 James A. Deye, Chairman James E. Rodgers, Vice Chair Raymond K. Wu, Vice Chair Structural Shielding Design and Evaluation for Peter J. Biggs Patton H. McGinley Megavoltage x- and Gamma-ray Radiotherapy Facilities Richard C. McCall Liaisons Kenneth R. Kase Marc Edwards Raymond K. Wu, PhD Consultants OhioHealth Hospitals Robert O. Gorson Jeffrey H. Kleck Nisy E. Ipe Columbus, OH Secretariat Marvin Rosenstein Eric E. Kearsley Learn • Calculation methods • W, U, T, IDR, TADR, RW, Rh, • Dose at maze door • Neutron, capture gamma at door • Laminated primary barrier This Report addresses the structural shielding design New Issues since NCRP # 49 and evaluation for medical use of megavoltage x- and gamma-rays for radiotherapy and supersedes related – New types of equipment, material in NCRP Report No. 49, Structural Shielding – Some with energies above 10 MV, Design and Evaluation for Medical Use of X Rays and Gamma Rays of Energies Up to 10 MeV, which was – Many new uses for radiotherapy equipment, issued in September 1976. – Dual energy machines, The descriptive information in NCRP Report No. 49 unique to x-ray therapy installations of less than 500 – Room designs without mazes, kV (Section 6.2) and brachytherapy is not included in – Varied shielding materials including composites, this Report and that information in NCRP Report No. 49 for those categories is still applicable. – More published data on empirical methods. -
Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion
United States Office of EPA-520/1-88-020 Environmental Protection Radiation Program September 1988 Agency Washington, DC 20460 Radiation EPA Limiting Values of Radionuclide Intake And Air Concentration and Dose Conversion Factors For Inhalation, Submersion, And Ingestion Federal Guidance Report No.11 This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees makes any warranty express or implied, or assumes any legal liability of responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency I thereof. This report was prepared by the OFFICE OF RADIATION PROGRAMS U.S. ENVIRONMENTAL PROTECTION AGENCY Washington, DC 20460 and by the OAK RIDGE NATIONAL LABORATORY Oak Ridge. Tennessee 37831 operated by MARTIN MARIE-I-I-A ENERGY SYSTEMS, INC. for the U.S. DEPARTMENT OF ENERGY Contract No. DE-ACO5-84OR21400 FEDERAL GUIDANCE REPORT NO. 11 LIMITING VALUES OF RADIONUCLIDE INTAKE AND AIR CONCENTRATION AND DOSE CONVERSION FACTORS FOR INHALATION, SUBMERSION, AND INGESTION Derived Guides for Control of Occupational Exposure and Exposure-to-Dose Conversion Factors for General Application, Based on the 1987 Federal Radiation Protection Guidance Keith F. -
Radiological Emissions-I
Radiological Emissions-I Ghulam Rasul Athar Applied Systems Analysis Group, Pakistan Atomic Energy Commission, P.O. Box 1114, Islamabad, Pakistan [email protected] IAEA Workshop on the ‘Use of the SimPacts Model for Estimating Human Health and Environmental Damages from Electricity Generation’ Trieste, Italy, May 12-23, 2003. Overview of the Presentation • Explanation of some terms used in radiation protection • Nuclear fuel cycle • NukPacts Becquerel (Bq) Becquerel is the basic unit of radioactivity. One Becquerel is equal to one disintegration per second. 1 Bq=2.7E-11 Ci One Ci = 3.7E+10 Bq Absorbed Dose When ionizing radiation interacts with the human body, it gives its energy to the body tissues. The amount of energy absorbed per unit weight of the organ or tissue is called absorbed dose. Absorbed dose is expressed in units of gray (Gy). One gray dose is equivalent to one joule radiation energy absorbed per kilogram of organ or tissue weight. Rad is the old and still used unit of absorbed dose. One gray is equivalent to 100 rads. (1 Gy = 100 rads) Equivalent Dose • Equal doses of all types of ionizing radiation are not equally harmful. • Alpha particles produce greater harm than do beta particles, gamma rays and x rays for a given absorbed dose. • To account for this difference, radiation dose is expressed as equivalent dose. • Equivqlent Dose is equal to "absorbed dose" multiplied by a "radiation weighting factor" (WR). • Equivalent Dose is measured in Sievert (Sv). • The dose in Sv (Equivalent Dose) = Dose x WR. • Prior to 1990, this weighting factor was referred to as Quality Factor (QF). -
Polonium-210
Health Physics Society Fact Sheet Adopted: May 2010 Revised: June 2020 Health Physics Society Specialists in Radiation Safety Polonium-210 General In 1898, Marie and Pierre Curie discovered their first radioactive* element. It was later named polonium in honor of Marie Sklodowska Curie’s native Poland. Polonium, a naturally occurring element that can be found throughout our environment, results from the radioactive decay of radon-222 gas—a part of the uranium-238 decay chain. There are over 30 known isotopes of polonium, and all are radioactive, but the one occurring most in nature—and the one most widely used—is polonium-210 (210Po). With a half-life of 138 days, it decays to stable lead-206 by the emission of an alpha particle (an alpha particle has two protons and two neutrons). Radioactive materials are quantified by activity, or the number of disintegrations that occur over a period of time. A terabecquerel (TBq), for instance, is equal to 1 x 1012 disintegrations per second. Polonium-210 has a very high specific activity—activity per unit mass—of about 166 TBq per gram (4,490 curies, Ci, per gram). In other words, it doesn’t take a large physical amount to be very radioactive. Because of the high specific activity and the large associated thermal cross section, according to a human health fact sheet for 210Po produced by Argonne National Laboratory, a capsule containing about 0.5 grams (83 TBq) of 210Po can reach temperatures exceeding 500o C (ANL 2005). When it is purified, polonium melts at a low temperature and can be quite volatile. -
Tritium (Hydrogen-3)
Human Health Fact Sheet ANL, October 2001 Tritium (Hydrogen-3) What Is It? Tritium is the only radioactive isotope of hydrogen. (An Symbol: H (H-3) isotope is a different form of an element that has the same number of protons in the nucleus but a different number of neutrons.) The nucleus Atomic Number: 1 of a tritium atom consists of a proton and two neutrons. This contrasts (protons in nucleus) with the nucleus of an ordinary hydrogen atom (which consists solely of a Atomic Weight: 1 proton) and a deuterium atom (which consists of one proton and one (naturally occurring H) neutron). Ordinary hydrogen comprises over 99.9% of all naturally occurring hydrogen. Deuterium comprises about 0.02%, and tritium comprises about a billionth of a billionth (10-18) percent. The most common Radioactive Properties of Tritium forms of tritium are tritium gas Half- Natural Specific Radiation Energy (MeV) Decay (HT) and tritium Isotope Life Abundance Activity Mode Alpha Beta Gamma oxide, also called (yr) (%) (Ci/g) (α) (β) (γ) “tritiated water.” H-3 12 a trillionth 9,800 β - 0.0057 - In tritiated water, a tritium atom Ci = curie, g = gram, and MeV = million electron volts; a dash means the entry is not applicable. (See the companion fact sheet on Radioactive Properties, Internal replaces one of the Distribution, and Risk Coefficients for an explanation of terms and interpretation of hydrogen atoms so radiation energies.) Values are given to two significant figures. the chemical form is HTO rather than H2O. The chemical properties of tritium are essentially the same as those of ordinary hydrogen.