DOE-HDBK-1079-94; Primer on Tritium Safe Handling Practices
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Nuclear Threat
MANAGEMENT OF RADIOLOGIC CASUALTIES Nuclear Threat . Formerly .Soviet Union .Nuclear fallout . Now .NBC threat against civilians .Accidental exposure of workers and public Images: CIA, FBI Accidental Exposure in Brazil . Cesium-137 source found by scavengers in 1987 . Source broken open, contents shared . 112,800 surveyed for contamination . 120 externally contaminated only . 129 internally & externally contaminated . 20 required hospital treatment . 14 developed bone marrow depression . 8 treated with Granulocyte Macrophage Colony-Stimulating Factors (GM-CSF) . 4 died acute phase, hemorrhage, infection . 1 died in 1994 from liver failure Images: CIA Medical Staff Exposure Medical staff received doses: . Maximum 500 millirem (5 millisieverts) .Natural background radiation dose ~ 200 millirems annually . Average 20 millirem (0.2 millisieverts) .Equivalent to one chest X-ray Juarez, Mexico Incident . 400 curies of cobalt-60 in stainless steel therapy device sold for scrap . Ended up in recycled steel rebar . Wrong turn into Los Alamos lab . I0 people significantly exposed . 1 construction worker died .bone cancer . 109 houses demolished in Mexico Images: CIA US Experience 1944-1999 . 243 radiation accidents leading to “serious” classification . 790 people received significant exposure resulting in 30 fatalities .Incidents included: . 137 industrial . 80 medical . 11 criticality Image: DOE The Basics of Radiation Radiation is energy that comes from a source and travels through matter or space Radioactivity is the spontaneous emission of radiation: . Either directly from unstable atomic nuclei, or . As a consequence of a nuclear reaction, or . Machine – produced (X-ray) Image: NOAA Contamination . Defined as internal or external deposition of radioactive particles . Irradiation continues until source removed by washing, flushing or radioactive decay . -
Power Sources Challenge
POWER SOURCES CHALLENGE FUSION PHYSICS! A CLEAN ENERGY Summary: What if we could harness the power of the Sun for energy here on Fusion reactions occur when two nuclei come together to form one Earth? What would it take to accomplish this feat? Is it possible? atom. The reaction that happens in the sun fuses two Hydrogen atoms together to produce Helium. It looks like this in a very simplified way: Many researchers including our Department of Energy scientists and H + H He + ENERGY. This energy can be calculated by the famous engineers are taking on this challenge! In fact, there is one DOE Laboratory Einstein equation, E = mc2. devoted to fusion physics and is committed to being at the forefront of the science of magnetic fusion energy. Each of the colliding hydrogen atoms is a different isotope of In order to understand a little more about fusion energy, you will learn about hydrogen, one deuterium and one the atom and how reactions at the atomic level produce energy. tritium. The difference in these isotopes is simply one neutron. Background: It all starts with plasma! If you need to learn more about plasma Deuterium has one proton and one physics, visit the Power Sources Challenge plasma activities. neutron, tritium has one proton and two neutrons. Look at the The Fusion Reaction that happens in the SUN looks like this: illustration—do you see how the mass of the products is less than the mass of the reactants? That is called a mass deficit and that difference in mass is converted into energy. -
The Design and Construction of an Ionization Chamber to Measure Background Radiation
AN ABSTRACT OF THE THESIS OF KENNETH EARL WEAVER for theMaster of Science (Name of Student) (Degree) in General Science (Radiological Physics) presented on August 19, 1968 (Major) (Date) Title: THE DESIGN AND CONSTRUCTION OF AN IONIZATION CHAMBER TO MEASURE BACKGROUND RADIATION Redacted for privacy Abstract approved: John P. Kelley An ionization chamber was constructed, using a fiberglass wall sphere, for the purpose of measuring background radiation.The system consists of the fiberglass wall chamber, 38.85 liters in volume, air filled, not sealed, used in conjunction with a precision capacitor, nulling voltage supply and electrometer.It was calibrated against a Shonka, 16.5 liter, muscle-equivalent, sealed ionization chamber in conjunction with a Shonka electrometer. Measurements made over a period extending from July 22 to July 29, 1968 in a second floor laboratory (X-ray Science and Engi- neering Laboratory, Oregon State University) with the fiberglass chamber yielded a mean dose rate of 7.96± 0.21 p. rads/hr.Meas- urements made over the same period with the Shonka system yielded a mean dose rate of 7.73 0.07 y, rads/hr. The Shonka system was also used to measure background radiation as a function of time from December 14, 1967 to June 10, 1968.The mean value obtained over this period was 7.73 ± 0.10 11 rads/hr. The Design and Construction of an Ionization Chamber to Measure Background Radiation by Kenneth Earl Weaver A THESIS submitted to Oregon State University in partial fulfillment of the requirements for the degree of Master of Science June 1969 APPROVED: Redacted for privacy Associate Professor of Electrical Engin4ring in charge of major Redacted for privacy -Chairman of the Dp-partment of Gene/''al ScienyCe Redacted for privacy Dean of Graduate School Date thesis is presented August 19, 1968 Typed by Carolyn Irving for Kenneth Earl Weaver ACKNOWLEDGMENT The author wishes to express hissincere appreciation to Mr. -
Characterization of a Homemade Ionization Chamber for Radiotherapy Beams
Applied Radiation and Isotopes 70 (2012) 1291–1295 Contents lists available at SciVerse ScienceDirect Applied Radiation and Isotopes journal homepage: www.elsevier.com/locate/apradiso Characterization of a homemade ionization chamber for radiotherapy beams Lucio P. Neves a,n, Ana P. Perini a, Gelson P. dos Santos a, Marcos Xavier a, Helen J. Khoury b, Linda V.E. Caldas a a Instituto de Pesquisas Energe´ticas e Nucleares (IPEN-CNEN/SP), Comissao~ Nacional de Energia Nuclear, Av. Prof. Lineu Prestes 2242, 05508-000 Sao~ Paulo, Brazil b Universidade Federal de Pernambuco, Departamento de Energia Nuclear, Av. Prof. Luiz Freire 1000, 50740-540 Recife, Brazil article info abstract Available online 30 November 2011 A homemade cylindrical ionization chamber was studied for routine use in therapy beams of 60Co and Keywords: X-rays. Several characterization tests were performed: leakage current, saturation, ion collection Cylindrical ionization chamber efficiency, polarity effect, stability, stabilization time, chamber orientation and energy dependence. Radiotherapy All results obtained were within international recommendations. Therefore the homemade ionization Calibration procedures chamber presents usefulness for routine dosimetric procedures in radiotherapy beams. & 2011 Elsevier Ltd. All rights reserved. 1. Introduction In order to contribute with the calibration procedures at LCI, in this work a homemade ionization chamber, designed and devel- Radiotherapy is well known and widely used in oncological oped at LCI, for calibration procedures in 60Co beams was treatment practice. Nowadays, a lot of research has been done in characterized. order to improve the treatments involving radiotherapy. These The operational tests were: leakage current, saturation, ion improvements include organ-sparing treatments and local control collection efficiency, polarity effect, stability, stabilization time, of the dose delivery, resulting in a reduction of the patient dose chamber orientation and energy dependence. -
Low-Cost Radon Detector with Low-Voltage Air-Ionization Chamber
sensors Article Low-Cost Radon Detector with Low-Voltage Air-Ionization Chamber Filip Studniˇcka 1,†, Jan Štˇepán 2,† and Jan Šlégr 1,∗,† 1 Department of Physics, Faculty of Science, University of Hradec Králové, Rokitanského 62, 500 03 Hradec Králové, Czech Republic 2 Center of Advanced Technology, Faculty of Science, University of Hradec Králové, Rokitanského 62, 500 03 Hradec Králové, Czech Republic * Correspondence: [email protected]; Tel.: +420-493-33-2773 † These authors contributed equally to this work. Received: 20 July 2019; Accepted: 25 August 2019; Published: 28 August 2019 Abstract: This paper describes the design of a low-cost radon detector that can easily be fabricated in large quantities for the purposes of earthquake prediction. The described detector can also be used for monitoring radon levels in houses because high radon levels pose a great health risk. A very simple air-ionization chamber for alpha particles was used, considering the experimental results. Chamber current-sensing circuitry is also suggested, and an Internet of Things (IoT) sensor grid is described. The main advantages of this detector are the low cost, low power consumption, and complete elimination of high-voltage power sources. The minimum detectable activity achieved with the proposed detector for one measurement was around 50 Bq · m−3, with time of measurement comparable to that featured on commercial devices, while the price of the described detector is one order of magnitude lower. Keywords: charge-carrier processes; ionizing radiation sensors; wireless sensor networks 1. Introduction Earthquake prediction (a branch of seismology concerned with the specification of the time, location, and magnitude of future earthquakes [1]) uses several physical parameters to assess the probability of an impending earthquake. -
Hydrogen and Its Components
HYDROGEN AND ITS COMPONENTS Discovery In 1671, Robert Boyle discovered and described the reaction between iron filings and dilute acids, which resulted in the production of hydrogen gas. In 1766-81, Henry Cavendish was the first to recognize that hydrogen gas was a discrete substance, and that it produced water when burned. He named it "flammable air". In 1783, Antoine Lavoisier gave the element the name hydrogen (from the Greek σδρο-hydro meaning "water" and -γενης genes meaning "creator") when he and Pierre-Simon Laplace reproduced Cavendish's finding that water was produced when hydrogen was burned. Hydrogen was liquefied for the first time by James Dewar in 1898 by using regenerative cooling and his invention, the vacuum flask. He produced solid hydrogen the next year. Deuterium was discovered in December 1931 by Harold Urey, and tritium was prepared in 1934 by Ernest Rutherford, Mark Oliphant, and Paul Harteck. Heavy water, which consists of deuterium in the place of regular hydrogen, was discovered by Urey's group in 1932. The nickel hydrogen battery was used for the first time in 1977 aboard the U.S. Navy's Navigation technology satellite-2 (NTS-2). It had two caesium atomic clocks on board and helped to show that satellite navigation based on precise timing was possible. In the dark part of its orbit, the Hubble Space Telescope is powered by nickel-hydrogen batteries, which were finally replaced in May 2009, more than 19 years after launch, and 13 years passed their design life. from NASA (accessed 2 Feb 2015) Isotopes of hydrogen Hydrogen has three naturally occurring isotopes, denoted 1H, 2H and 3H. -
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. -
Ionization Chamber Type Survey Instruments
Chapter 5: Instrumentation Objectives: • Summarize the advantages and disadvantages of the different types of devices used to monitor individuals for radiation exposure. • Describe the principal advantages and disadvantages of air ionization chamber type survey instruments. • Describe the principal advantages and disadvantages of Geiger-Müller (GM) type survey instruments. SAT Chapter 5 - Instrumentation 2 Objectives: • Describe the important characteristics of any radiation monitoring instrument and why these characteristics are important for obtaining accurate results. • Select the appropriate survey instrument for a task, and be able to ensure its proper operation and be able to interpret the results obtained. SAT Chapter 5 - Instrumentation 3 Overview: • Humans cannot detect ionizing radiation with any of our senses. But, we need to know: – Is ionizing radiation present? – Are we receiving dose from ionizing radiation? – How much dose have we received (mrem)? – Is there contamination present? • We use instruments which respond to ionizing radiation. The type of instrument needed depends on the type and levels of radiation that are present. • Radiation detectors respond to ionizations or excitations created by radiation interaction with the detector media. Detectors can either be gas-filled or solid materials. SAT Chapter 5 - Instrumentation 4 Instrumentation Gas-filled instruments for detecting ionizing radiation utilize the concept that radiation interaction with atoms can cause ionizations. The ions are collected and measured. This is used to provide information on the presence of radioactive material (contamination) or the dose rate in an area. Hi + Volt - Ionizing Radiation (MEDIUM) SAT Chapter 5 - Instrumentation 5 IONIZATION CURVE 1015 I II III IV V VI 1012 Proportional 109 Continuous Geiger- Discharge Müller 106 α # of Ion Pairs Collected Pairs Ion of # 103 β 0 0 200 400 600 800 1000 1200 1400 1600 Applied Voltage, V SAT Chapter 5 - Instrumentation 6 Ionization Chamber Ionization chambers measure the ionization of air. -
Radiation Dosimetry
Radiation Dosimetry AGEN-698 Advances in Food Engineering Introduction Radiation dosimetry is the branch of science that attempts to quantitatively relate specific measurement in a radiation field to chemical and/or biological changes that the radiation would produce in a target Radiation When radiation interact with matter it produces: Excited and ionized atoms and molecules A large number of secondary electrons Exposure It is defined for gamma and X- rays in terms of the amount of ionization they produce in air Units: roentgen [R] – 1 R = 2.58x10-4 C/kg ∆Q is the sum of all charges of one sign produced in air when ∆Q all the electrons liberated by Exposure = photons in a mass ∆m of air ∆m are completely stopped in air Applies only to electromagnetic radiation and the mass and roentgen refer only to air Absorbed dose The energy absorbed per unit mass from any kind 1J 107 erg of ionizing radiation in 1Gy ≡ = = any kind of matter kg 103 g Traditional unit: rad = erg = 104 = 100rad 100 erg/g g New SI unit: gray (Gy) Absorbed dose is often referred to simply as the dose Dose equivalent The absorbed dose to achieve a given level of biological damage (e.g., 50% cell killing) is often different for different kinds of radiation H = QD Equivalent dose, H, is defined as the product of the absorbed dose D and the dimensionless quantity Q, which depends on LET Dependence of Q on LET LET [MeV/cm] Q 3.5 or less 1 3.5-7.0 1-2 7.0-23 2-5 23-53 5-10 53-175 10-20 γ-rays, X-rays, electrons, 1 positrons of any LET Measurement of Exposure Exposure -
Internal and External Exposure Exposure Routes 2.1
Exposure Routes Internal and External Exposure Exposure Routes 2.1 External exposure Internal exposure Body surface From outer space contamination and the sun Inhalation Suspended matters Food and drink consumption From a radiation Lungs generator Radio‐ pharmaceuticals Wound Buildings Ground Radiation coming from outside the body Radiation emitted within the body Radioactive The body is equally exposed to radiation in both cases. materials "Radiation exposure" refers to the situation where the body is in the presence of radiation. There are two types of radiation exposure, "internal exposure" and "external exposure." External exposure means to receive radiation that comes from radioactive materials existing on the ground, suspended in the air, or attached to clothes or the surface of the body (p.25 of Vol. 1, "External Exposure and Skin"). Conversely, internal exposure is caused (i) when a person has a meal and takes in radioactive materials in the food or drink (ingestion); (ii) when a person breathes in radioactive materials in the air (inhalation); (iii) when radioactive materials are absorbed through the skin (percutaneous absorption); (iv) when radioactive materials enter the body from a wound (wound contamination); and (v) when radiopharmaceuticals containing radioactive materials are administered for the purpose of medical treatment. Once radioactive materials enter the body, the body will continue to be exposed to radiation until the radioactive materials are excreted in the urine or feces (biological half-life) or as the radioactivity weakens over time (p.26 of Vol. 1, "Internal Exposure"). The difference between internal exposure and external exposure lies in whether the source that emits radiation is inside or outside the body. -
Conception and Realization of a Parallel-Plate Free-Air Ionization
Conception and realization of a parallel-plate free-air ionization chamber for the absolute dosimetry of an ultrasoft X-ray beam J.-E Groetz, Nabil Ounoughi, C Mavon, A Belafrites, M Fromm To cite this version: J.-E Groetz, Nabil Ounoughi, C Mavon, A Belafrites, M Fromm. Conception and realization of a parallel-plate free-air ionization chamber for the absolute dosimetry of an ultrasoft X-ray beam. Re- view of Scientific Instruments, American Institute of Physics, 2014, 85, pp.83304. 10.1063/1.4890817. hal-01117735 HAL Id: hal-01117735 https://hal.archives-ouvertes.fr/hal-01117735 Submitted on 17 Feb 2015 HAL is a multi-disciplinary open access L’archive ouverte pluridisciplinaire HAL, est archive for the deposit and dissemination of sci- destinée au dépôt et à la diffusion de documents entific research documents, whether they are pub- scientifiques de niveau recherche, publiés ou non, lished or not. The documents may come from émanant des établissements d’enseignement et de teaching and research institutions in France or recherche français ou étrangers, des laboratoires abroad, or from public or private research centers. publics ou privés. Conception and realization of a parallel-plate free-air ionization chamber for the absolute dosimetry of an ultrasoft X-ray beam J.-E. Groetz,1, a) N. Ounoughi,1, 2 C. Mavon,1 A.Belafrites,2 and M. Fromm1 1)Laboratoire Chrono-Environnement UMR CNRS 6249, 5 Universit´ede Franche-Comt´e,16 route de Gray, 25030 Besan¸conCedex, France 2)Laboratoire de Physique des Rayonnements et Applications, Universit´ede Jijel, B.P. 98 Ouled Aissa, Jijel 18000, Alg´erie (Dated: 20 June 2014) 10 We report the design of a millimeter-sized parallel plate free-air ionization chamber (IC) aimed at determining the absolute air kerma rate of an ultra-soft X-ray beam (E = 1:5 keV). -
Basics of Radiation Dosimetry for the Physicist
Basics of Radiation Dosimetry for the Physicist http://en.wikipedia.org/wiki/Ionizing_radiation I. Ionizing radiation consists of subatomic particles or electromagnetic waves that ionize electrons along their path in traversing materials. Examples of ionizing particles are energetic alpha particles, beta particles, protons, and neutrons. The ability of a photons to ionize depends on the wavelength. Radiation on the short wavelength end of the electromagnetic spectrum - ultraviolet, x-rays, and gamma rays - are ionizing radiation. Longer waves, near-UV, infrared are damaging but not considered ionizing radiation. The energy loss of a particle −(dE / dx) is related to energy absorbed by the medium, “linear energy transfer”, LET. The LET plays an important role in the absorbed dose given to a material or body when exposed to ionizing radiation. LET ! −(dE / dx) II. Absorbed Dose and Dose rate The unit of absorbed dose D for ionizing radiation is the Gray. It is defined as the energy deposited in Joules per kilogram of material. The cgs unit of absorbed dose is the rad, and is slowly being phased out. 1 Gy= 1 J/kG 1Gy=100 rad 1 dE < E( J)> D = !∫ dx ≈ dose mV V dx m(kg) dD < dE /dt > ⎡ J /s ⎤ A = = dose rate D dt m ⎢ kg ⎥ ⎣ ⎦ III. Restricted LET The LET in a target represents the degradation of energy of the incident beam particle along its quasi- linear path. But this may not strictly be equivalent to the energy absorbed in the target! This is due to the fact that the −(dE / dx) may not be localized, as energy may be deposited well away from the particles line of flight.