What Is Ionizing Radiation Fact Sheet
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R-Process Elements from Magnetorotational Hypernovae
r-Process elements from magnetorotational hypernovae D. Yong1,2*, C. Kobayashi3,2, G. S. Da Costa1,2, M. S. Bessell1, A. Chiti4, A. Frebel4, K. Lind5, A. D. Mackey1,2, T. Nordlander1,2, M. Asplund6, A. R. Casey7,2, A. F. Marino8, S. J. Murphy9,1 & B. P. Schmidt1 1Research School of Astronomy & Astrophysics, Australian National University, Canberra, ACT 2611, Australia 2ARC Centre of Excellence for All Sky Astrophysics in 3 Dimensions (ASTRO 3D), Australia 3Centre for Astrophysics Research, Department of Physics, Astronomy and Mathematics, University of Hertfordshire, Hatfield, AL10 9AB, UK 4Department of Physics and Kavli Institute for Astrophysics and Space Research, Massachusetts Institute of Technology, Cambridge, MA 02139, USA 5Department of Astronomy, Stockholm University, AlbaNova University Center, 106 91 Stockholm, Sweden 6Max Planck Institute for Astrophysics, Karl-Schwarzschild-Str. 1, D-85741 Garching, Germany 7School of Physics and Astronomy, Monash University, VIC 3800, Australia 8Istituto NaZionale di Astrofisica - Osservatorio Astronomico di Arcetri, Largo Enrico Fermi, 5, 50125, Firenze, Italy 9School of Science, The University of New South Wales, Canberra, ACT 2600, Australia Neutron-star mergers were recently confirmed as sites of rapid-neutron-capture (r-process) nucleosynthesis1–3. However, in Galactic chemical evolution models, neutron-star mergers alone cannot reproduce the observed element abundance patterns of extremely metal-poor stars, which indicates the existence of other sites of r-process nucleosynthesis4–6. These sites may be investigated by studying the element abundance patterns of chemically primitive stars in the halo of the Milky Way, because these objects retain the nucleosynthetic signatures of the earliest generation of stars7–13. -
Glossary Derived From: Human Research Program Integrated Research Plan, Revision A, (January 2009)
Glossary derived from: Human Research Program Integrated Research Plan, Revision A, (January 2009). National Aeronautics and Space Administration, Johnson Space Center, Houston, Texas 77058, pages 232-280. Report No. 153: Information Needed to Make Radiation Protection Recommendations for Space Missions Beyond Low-Earth Orbit (2006). National Council on Radiation Protection and Measurements, pages 309-318. Reprinted with permission of the National Council on Radiation Protection and Measurements, http://NCRPonline.org . Managing Space Radiation Risk in the New Era of Space Exploration (2008). Committee on the Evaluation of Radiation Shielding for Space Exploration, National Research Council. National Academies Press, pages 111-118. -A- AAPM: American Association of Physicists in Medicine. absolute risk: Expression of excess risk due to exposure as the arithmetic difference between the risk among those exposed and that obtaining in the absence of exposure. absorbed dose (D): Average amount of energy imparted by ionizing particles to a unit mass of irradiated material in a volume sufficiently small to disregard variations in the radiation field but sufficiently large to average over statistical fluctuations in energy deposition, and where energy imparted is the difference between energy entering the volume and energy leaving the volume. The same dose has different consequences depending on the type of radiation delivered. Unit: gray (Gy), equivalent to 1 J/kg. ACE: Advanced Composition Explorer Mission, launched in 1997 and orbiting the L1 libration point to sample energetic particles arriving from the Sun and interstellar and galactic sources. It also provides continuous coverage of solar wind parameters and solar energetic particle intensities (space weather). When reporting space weather, it can provide an advance warning (about one hour) of geomagnetic storms that can overload power grids, disrupt communications on Earth, and present a hazard to astronauts. -
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. -
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 ..................................................................... -
Cherenkov Radiation
TheThe CherenkovCherenkov effecteffect A charged particle traveling in a dielectric medium with n>1 radiates Cherenkov radiation B Wave front if its velocity is larger than the C phase velocity of light v>c/n or > 1/n (threshold) A β Charged particle The emission is due to an asymmetric polarization of the medium in front and at the rear of the particle, giving rise to a varying electric dipole momentum. dN Some of the particle energy is convertedγ = 491into light. A coherent wave front is dx generated moving at velocity v at an angle Θc If the media is transparent the Cherenkov light can be detected. If the particle is ultra-relativistic β~1 Θc = const and has max value c t AB n 1 cosθc = = = In water Θc = 43˚, in ice 41AC˚ βct βn 37 TheThe CherenkovCherenkov effecteffect The intensity of the Cherenkov radiation (number of photons per unit length of particle path and per unit of wave length) 2 2 2 2 2 Number of photons/L and radiation d N 4π z e 1 2πz 2 = 2 1 − 2 2 = 2 α sin ΘC Wavelength depends on charge dxdλ hcλ n β λ and velocity of particle 2πe2 α = Since the intensity is proportional to hc 1/λ2 short wavelengths dominate dN Using light detectors (photomultipliers)γ = sensitive491 in 400-700 nm for an ideally 100% efficient detector in the visibledx € 2 dNγ λ2 d Nγ 2 2 λ2 dλ 2 2 11 1 22 2 d 2 z sin 2 z sin 490393 zz sinsinΘc photons / cm = ∫ λ = π α ΘC ∫ 2 = π α ΘC 2 −− 2 = α ΘC λ1 λ1 dx dxdλ λ λλ1 λ2 d 2 N d 2 N dλ λ2 d 2 N = = dxdE dxdλ dE 2πhc dxdλ Energy loss is about 104 less hc 2πhc than 2 MeV/cm in water from € -
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). -
3 Gamma-Ray Detectors
3 Gamma-Ray Detectors Hastings A Smith,Jr., and Marcia Lucas S.1 INTRODUCTION In order for a gamma ray to be detected, it must interact with matteu that interaction must be recorded. Fortunately, the electromagnetic nature of gamma-ray photons allows them to interact strongly with the charged electrons in the atoms of all matter. The key process by which a gamma ray is detected is ionization, where it gives up part or all of its energy to an electron. The ionized electrons collide with other atoms and liberate many more electrons. The liberated charge is collected, either directly (as with a proportional counter or a solid-state semiconductor detector) or indirectly (as with a scintillation detector), in order to register the presence of the gamma ray and measure its energy. The final result is an electrical pulse whose voltage is proportional to the energy deposited in the detecting medhtm. In this chapter, we will present some general information on types of’ gamma-ray detectors that are used in nondestructive assay (NDA) of nuclear materials. The elec- tronic instrumentation associated with gamma-ray detection is discussed in Chapter 4. More in-depth treatments of the design and operation of gamma-ray detectors can be found in Refs. 1 and 2. 3.2 TYPES OF DETECTORS Many different detectors have been used to register the gamma ray and its eneqgy. In NDA, it is usually necessary to measure not only the amount of radiation emanating from a sample but also its energy spectrum. Thus, the detectors of most use in NDA applications are those whose signal outputs are proportional to the energy deposited by the gamma ray in the sensitive volume of the detector. -
Sources of Gamma Radiation in a Reactor Core Matts Roas
AE-19 Sources of gamma radiation in a reactor core Matts Roas AKTIEBOLAGET ATOMENERGI STOCKHOLM • S\\ HDJtN • 1959 AE-19 ERRATUM The spectrum in Fig. 3 has erroneously been normalized to 7. 4 MeV/capture. The correct spectrum can be found by mul- tiplying the ordinate by 0. 64. AE-19 Sources of gamma radiation in a reactor core Matts Roos Summary: - In a thermal reactor the gamma ray sources of importance for shielding calculations and related aspects are 1) fission, 2) decay of fission products, 3) capture processes in fuel, poison and other materials, 4) inelastic scattering in the fuel and 5) decay of capture products. The energy release and the gamma ray spectra of these sources have been compiled or estimated from the latest information available, and the results are presented in a general way to permit 235 application to any thermal reactor, fueled with a mixture of U and 238 U • As an example the total spectrum and the spectrum of radiation escaping from a fuel rod in the Swedish R3-reactor are presented. Completion of manuscript April 1959 Printed Maj 1959 LIST OF CONTENTS Page Introduction ........... 1 1. Prompt fis sion gamma rays i 2. Fission product gamma rays 2 3. Uranium capture gamma rays 4 O -2 Q 4. U inelastic scattering gamma rays 5 5. Gamma rays from capture in poison, construction materials and moderator .....*•»..•........ 8 6. Gamma rays from disintegration of capture products. 8 7. Total gamma spectra. Application to the Swedish R3 -reactor 9 SOURCES OF GAMMA RADIATION IN A REACTOR CORE. -
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. -
Slow Neutrons and Secondary Gamma Ray Distributions in Concrete Shields Followed by Reflecting Layers
oo A. R. E. A. E. A. / Rep. 318 w ARAB REPUBLIC OF EGYPT ATOMIC ENERGY AUTHORITY REACTOR AND NEUTRON PHYSICS DEPART SLOW NEUTRONS AND SECONDARY GAMMA RAY DISTRIBUTIONS IN CONCRETE SHIELDS FOLLOWED BY REFLECTING LAYERS BY A.S. MAKARI.OUS, Y;I. SWILEM, Z. AWWAD AND T. BAYOMY 1993 INFORMATION AND DOCUMENTATION CENTER ATOMIC ENERGY POST OFFICE CAIRO, A.R;I:. VOL 2 7 id Q 7 AREAEA/Rep.318 ARAB REPUBLIC OF EGYPT ATOMIC ENERGY AUTHORITY REACTOR AND NEUTRON PHYSICS DEPART, SLOW NEUTRONS AND SECONDARY GAMMA RAY DISTRIBUTIONS IN CONCRETE SHIELDS FOLLOWED BY REFLECTING LAYERS BY A,S.M\KARIOUS, Y.I.SWILEM, 2.AWWAD AND T.BAYOMY INFORMATION AND DUCUMENTATICN CENTER ATOMIC ENERGY POST OFFICE CAIRO, A.R«E. CONTENTS x Page ABSTRACT *<,..».»••... i INTRODUCTION . *« . *.*,...... 1 EXPERIMENTAL DETAILS ••»*«•««»« • • a • » « •»»«*««* *»»*«•»»»«»<>• — RESULTS AND DISCUSSION ..,.••+ .*.....•...•.. 4 ACKNOWLEDGEMENTS ...,.......•..<...»,..>......... 10 REFERENCES „...»,«.**»» 11 ABSTRACT Slow neutrons and secondary gamma r>ay distributions in concrete shields with and without a reflecting layer behind the concrete shield have been investigated first in case of' using a bare reactor beam and then on using & B.C filtered beam. The total and capture secondary gair-m-a ray coefficient (B^and B^) , the ratio of the reflected (Thermal neutron (S ) the ratio of the secondary gamma rays caused by reflected neutrons to those caused by transmitted neutrons ( and the effect of inserting a blocking l&yer (a B^C layer) between the concrete shield and the reflector on the sup- pression of the produced secondary gamma rays have been investigated, It was found that the presence of the reflector layer behind the concrete shield reflects sor/so thermal neutrons back to the concrete shields end so it increases the number of thermal neutrons at the interface between the concrete shield and the reflector. -
MIRD Pamphlet No. 22 - Radiobiology and Dosimetry of Alpha- Particle Emitters for Targeted Radionuclide Therapy
Alpha-Particle Emitter Dosimetry MIRD Pamphlet No. 22 - Radiobiology and Dosimetry of Alpha- Particle Emitters for Targeted Radionuclide Therapy George Sgouros1, John C. Roeske2, Michael R. McDevitt3, Stig Palm4, Barry J. Allen5, Darrell R. Fisher6, A. Bertrand Brill7, Hong Song1, Roger W. Howell8, Gamal Akabani9 1Radiology and Radiological Science, Johns Hopkins University, Baltimore MD 2Radiation Oncology, Loyola University Medical Center, Maywood IL 3Medicine and Radiology, Memorial Sloan-Kettering Cancer Center, New York NY 4International Atomic Energy Agency, Vienna, Austria 5Centre for Experimental Radiation Oncology, St. George Cancer Centre, Kagarah, Australia 6Radioisotopes Program, Pacific Northwest National Laboratory, Richland WA 7Department of Radiology, Vanderbilt University, Nashville TN 8Division of Radiation Research, Department of Radiology, New Jersey Medical School, University of Medicine and Dentistry of New Jersey, Newark NJ 9Food and Drug Administration, Rockville MD In collaboration with the SNM MIRD Committee: Wesley E. Bolch, A Bertrand Brill, Darrell R. Fisher, Roger W. Howell, Ruby F. Meredith, George Sgouros (Chairman), Barry W. Wessels, Pat B. Zanzonico Correspondence and reprint requests to: George Sgouros, Ph.D. Department of Radiology and Radiological Science CRB II 4M61 / 1550 Orleans St Johns Hopkins University, School of Medicine Baltimore MD 21231 410 614 0116 (voice); 413 487-3753 (FAX) [email protected] (e-mail) - 1 - Alpha-Particle Emitter Dosimetry INDEX A B S T R A C T......................................................................................................................... -
Nuclear Glossary
NUCLEAR GLOSSARY A ABSORBED DOSE The amount of energy deposited in a unit weight of biological tissue. The units of absorbed dose are rad and gray. ALPHA DECAY Type of radioactive decay in which an alpha ( α) particle (two protons and two neutrons) is emitted from the nucleus of an atom. ALPHA (ααα) PARTICLE. Alpha particles consist of two protons and two neutrons bound together into a particle identical to a helium nucleus. They are a highly ionizing form of particle radiation, and have low penetration. Alpha particles are emitted by radioactive nuclei such as uranium or radium in a process known as alpha decay. Owing to their charge and large mass, alpha particles are easily absorbed by materials and can travel only a few centimetres in air. They can be absorbed by tissue paper or the outer layers of human skin (about 40 µm, equivalent to a few cells deep) and so are not generally dangerous to life unless the source is ingested or inhaled. Because of this high mass and strong absorption, however, if alpha radiation does enter the body through inhalation or ingestion, it is the most destructive form of ionizing radiation, and with large enough dosage, can cause all of the symptoms of radiation poisoning. It is estimated that chromosome damage from α particles is 100 times greater than that caused by an equivalent amount of other radiation. ANNUAL LIMIT ON The intake in to the body by inhalation, ingestion or through the skin of a INTAKE (ALI) given radionuclide in a year that would result in a committed dose equal to the relevant dose limit .