INGESTION PATHWAY the Emergency Planning Zone (EPZ) for the Ingestion Pathway Extends to a Radius of 50 Miles Through 360 Degrees from a Nuclear Power Plant
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The Discoverers of the Ruthenium Isotopes
•Platinum Metals Rev., 2011, 55, (4), 251–262• The Discoverers of the Ruthenium Isotopes Updated information on the discoveries of the six platinum group metals to 2010 http://dx.doi.org/10.1595/147106711X592448 http://www.platinummetalsreview.com/ By John W. Arblaster This review looks at the discovery and the discoverers Wombourne, West Midlands, UK of the thirty-eight known ruthenium isotopes with mass numbers from 87 to 124 found between 1931 and 2010. Email: [email protected] This is the sixth and fi nal review on the circumstances surrounding the discoveries of the isotopes of the six platinum group elements. The fi rst review on platinum isotopes was published in this Journal in October 2000 (1), the second on iridium isotopes in October 2003 (2), the third on osmium isotopes in October 2004 (3), the fourth on palladium isotopes in April 2006 (4) and the fi fth on rhodium isotopes in April 2011 (5). An update on the new isotopes of palladium, osmium, iridium and platinum discovered since the previous reviews in this series is also included. Naturally Occurring Ruthenium Of the thirty-eight known isotopes of ruthenium, seven occur naturally with the authorised isotopic abun- dances (6) shown in Table I. The isotopes were fi rst detected in 1931 by Aston (7, 8) using a mass spectrograph at the Cavendish Laboratory, Cambridge University, UK. Because of diffi cult experimental conditions due to the use of poor quality samples, Aston actually only detected six of the isotopes and obtained very approximate Table I The Naturally Occurring Isotopes of Ruthenium Mass number Isotopic Abundance, % 96Ru 5.54 98Ru 1.87 99Ru 12.76 100Ru 12.60 101Ru 17.06 102Ru 31.55 104Ru 18.62 251 © 2011 Johnson Matthey http://dx.doi.org/10.1595/147106711X592448 •Platinum Metals Rev., 2011, 55, (4)• percentage abundances. -
General Guidelines for the Estimation of Committed Effective Dose from Incorporation Monitoring Data
Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaftt Wissenschaftliche Berichte FZKA 7243 General Guidelines for the Estimation of Committed Effective Dose from Incorporation Monitoring Data (Project IDEAS – EU Contract No. FIKR-CT2001-00160) H. Doerfel, A. Andrasi, M. Bailey, V. Berkovski, E. Blanchardon, C.-M. Castellani, C. Hurtgen, B. LeGuen, I. Malatova, J. Marsh, J. Stather Hauptabteilung Sicherheit August 2006 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Wissenschaftliche Berichte FZKA 7243 GENERAL GUIDELINES FOR THE ESTIMATION OF COMMITTED EFFECTIVE DOSE FROM INCORPORATION MONITORING DATA (Project IDEAS – EU Contract No. FIKR-CT2001-00160) H. Doerfel, A. Andrasi 1, M. Bailey 2, V. Berkovski 3, E. Blanchardon 6, C.-M. Castellani 4, C. Hurtgen 5, B. LeGuen 7, I. Malatova 8, J. Marsh 2, J. Stather 2 Hauptabteilung Sicherheit 1 KFKI Atomic Energy Research Institute, Budapest, Hungary 2 Health Protection Agency, Radiation Protection Division, (formerly National Radiological Protection Board), Chilton, Didcot, United Kingdom 3 Radiation Protection Institute, Kiev, Ukraine 4 ENEA Institute for Radiation Protection, Bologna, Italy 5 Belgian Nuclear Research Centre, Mol, Belgium 7 Institut de Radioprotection et de Sûreté Nucléaire, Fontenay-aux-Roses, France 8 Electricité de France (EDF), Saint-Denis, France 9 National Radiation Protection Institute, Praha, Czech Republic Forschungszentrum Karlsruhe GmbH, Karlsruhe 2006 Für diesen Bericht behalten wir uns alle Rechte vor Forschungszentrum Karlsruhe GmbH Postfach 3640, 76021 Karlsruhe Mitglied der Hermann von Helmholtz-Gemeinschaft Deutscher Forschungszentren (HGF) ISSN 0947-8620 urn:nbn:de:0005-072434 IDEAS General Guidelines – June 2006 Abstract Doses from intakes of radionuclides cannot be measured but must be assessed from monitoring, such as whole body counting or urinary excretion measurements. -
Carbon-14 Radiological Safety Guidance Revision Date: 09/27/18
Carbon-14 Radiological Safety Guidance Revision Date: 09/27/18 Physical Data BETA ENERGIES • 156.4 keV (maximum) • 49.5 keV (average) (100%) Physical Half-Life 5730 years Biological Half-Life 10 days (Whole Body) Effective Half-Life 10 days (Bound/Whole Body) Effective Half-Life 40 days (Unbound/Bone) Specific Activity 4460 millicuries/gram Maximum Beta Range in Air 25.400 cm = 10.0 inches Maximum Beta Range in Water/Tissue* 0.030 cm = 0.012 inches Maximum Range in Plexiglas/Lucite/Plastic 0.025 cm = 0.010 inches *Fraction of C-14 beta particles transmitted through dead layer of skin (0.007 cm) = 17% Shielding None required (≤ 3 mm plexiglass) Half-Value Layer (Water) 0.005 cm = 0.05 mm Tenth-Value Layer (Water) 0.017 cm = 0.17 mm Volatility • Inherent Volatility (STP) is Not Significant Exposure: Radiological Safety Information There are three main classes of carbon compounds which may be inhaled: organic compounds, gases (CO or CO2), and aerosols of carbon containing compounds such as carbonates and carbides. Carbon- 14 Data Sheet Page 1 of 4 Revision Date: 09/27/18 Exposure Rates Dose Rate from a 1.0 millicurie isotropic point source of C-14: DISTANCE RAD/HOUR 1.0 cm 1241.4 2.0 cm 250.4 15.2 cm 0.126 20.0 cm 0.0046 Exposure Prevention • Always wear a lab coat and disposable gloves when working with C-14. • Possibility of organic C-14 compounds being absorbed through gloves. Administrative Controls • Care should be taken not to generate CO2 gas that could be inhaled. -
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. -
Properties and Applications of Ruthenium
Chapter 17 Properties and Applications of Ruthenium Anil K. Sahu, Deepak K. Dash, Koushlesh Mishra, Saraswati P. Mishra, Rajni Yadav and Pankaj Kashyap Additional information is available at the end of the chapter http://dx.doi.org/10.5772/intechopen.76393 Abstract Ruthenium (Ru) with atomic number of 44 is one of the platinum group metals, the others being Rh, Pd, Os, Ir and Pt. In earth’s crust, it is quite rare, found in parts per billion quantities, in ores containing some of the other platinum group metals. Ruthenium is silvery whitish, lustrous hard metal with a shiny surface. It has seven stable isotopes. Recently, coordination and organometallic chemistry of Ru has shown remarkable growth. In this chapter, we review the application of Ru in diverse fields along with its physical and chemical properties. In the applications part of Ru we have primarily focused on the biomedical applications. The biomedical applications are broadly divided into diagnostic and treatment aspects. Ru and their complexes are mainly used in determination of ferritin, calcitonin and cyclosporine and folate level in human body for diagnosis of diseases. Treat- ment aspects focuses on immunosuppressant, antimicrobial and anticancer activity. Keywords: ruthenium, platinum group, biomedical application, rare element, cancer, isotopes 1. Discovery of ruthenium Ruthenium is one of the 118 chemical elements given in the periodic table. Out of these 118 elements, 92 elements originated from natural sources and remaining 26 elements have been synthesized in laboratories [1, 2]. The last naturally occurring element to be discovered was Uranium in 1789 [1, 3]. Technetium was the first man-made element to be synthesized in the year 1937 [2]. -
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. -
Safety Reports Series No
This publication focuses on the medical management Safety Reports Series of individuals involved in radiation emergencies, especially those with deterministic effects due Safety Reports Series to exposure to high doses of ionizing radiation. Its primary objective is to provide practical information to be used for treatment decisions by No. 101 medical personnel during a radiation emergency. 101 No. It also provides general and specific measures for the medical handling of individuals who have been internally contaminated with radionuclides. This publication complements other IAEA publications on the medical response to radiation emergencies. Medical Management of Radiation Injuries Medical Management of Radiation Injuries Jointly sponsored by PAHO OPS OPAS INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA ISBN 978–92–0–107019–7 ISSN 1020–6450 Atoms for Peace RELATED PUBLICATIONS Atoms for Peace IAEA SAFETY STANDARDS AND RELATED PUBLICATIONS FUNDAMENTAL SAFETY PRINCIPLES IAEA Safety Standards Series No. SF-1 IAEA SAFETY STANDARDS STI/PUB/1273 (21 pp.; 2006) Under the terms of Article III of its Statute, the IAEA is authorized to establish or adopt ISBN 92–0–110706–4 Price: €25.00 standards of safety for protection of health and minimization of danger to life and property, and to provide for the application of these standards. GOVERNMENTAL, LEGAL AND REGULATORY FRAMEWORK The publications by means of which the IAEA establishes standards are issued in the FOR SAFETY IAEA Safety Standards Series. This series covers nuclear safety, radiation safety, transport IAEA Safety Standards Series No. GSR Part 1 (Rev. 1) safety and waste safety. The publication categories in the series are Safety Fundamentals, STI/PUB/1713 (42 pp.; 2016) Safety Requirements and Safety Guides. -
Activation Cross Sections of Proton Induced Nuclear Reactions on Palladium up to 80 Mev
Activation cross sections of proton induced nuclear reactions on palladium up to 80 MeV F. Tark´ anyi´ a, F. Ditroi´ a,∗, S. Takacs´ a, J. Csikaia, A. Hermanneb, S. Uddind, M. Babad aInstitute for Nuclear Research, Hungarian Academy of Sciences (ATOMKI), Debrecen, Hungary bCyclotron Laboratory, Vrije Universiteit Brussel (VUB), Brussels, Belgium cInstitute of Physics and Power Engineering (IPPE), Obninsk, Russia dCyclotron Radioisotope Center (CYRIC), Tohoku University, Sendai, Japan Abstract Activation cross sections of proton induced nuclear reactions on palladium were measured up to 80 MeV by using the stacked foil irradiation technique and gamma ray spectrometry. The beam intensity, the incident energy and the energy degradation were controlled by a method based on flux constancy via normalization to the excitation functions of monitor reactions measured in parallel. Excitation functions for direct and cumulative cross-sections were measured for the production of 104m;104g;105g;106m;110mAg, 100;101Pd, 99m;99g;100;101m;101g;102m;102g;105Rh and 103;97Ru radioisotopes. The cross section data were compared with the theoretical predictions of TENDL-2014 and -2015 libraries. For practical applications thick target yields were derived from the measured excitation functions. Application in the field of medical radionuclide production is shortly discussed. Keywords: proton irradiation, palladium target, stacked foil technique, cross sections, production yields 1. Introduction Hu et al., 1998; Johnson et al., 1979; Kormali et al., 1976; Zarubin and Sergeev, 1989). Our results obtained Excitation functions of proton induced nuclear re- in that period for some medically relevant radionuclides actions on palladium are important in many applica- were published during 2004-2007. -
Introduction I C RP Publication 30 Dose-Equivalent Limits ICRP
STATEMENT FROM THE 1983 MEETING OF THE INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION The International Commission on Radiological Protection met in Washington, USA, in October, 1983. During the meeting the Commission identified the following points requiring clarification. Annual Limits on Intakes (ALl) and Derived Air Concentrations (DAC) for Members of the Public Introduction Exposure to radioactive materials must be constrained by the relevant dose-equivalent limits recommended in ICRP Publication 26 (1977) to reduce stochastic effects to an acceptable level and to prevent non-stochastic effects from occurring in the organs and tissues of the body. An ALl of a radionuclide or a DAC for submersion in an atmosphere contaminated with a radioactive chemically inert gas is then determined by the dose equivalent to which the organs and tissues of the body are committed as the result of such exposures. The values of ALJ and DAC recommended in I C RP Publication 30 are for workers based on a Reference Man; the factors by which they would differ from those that would be appropriate for members of the public are many and various, as discussed below. Dose-equivalent Limits For stochastic effects in members of the public the Commission recommends that the committed effective dose equivalent from exposure to radioactive materials in any year be limited to 5 mSv, and, for repeated exposures over prolonged periods, that it would be prudent further to restrict this to 1 mSv from each year of lifelong exposure. For an individual exposed over the whole lifetime, the committed effective dose equivalent will depend partly on the age-specific relationship between annual intakes and committed dose equivalent and partly on age-specific factors influencing the annual intake. -
RUTHENIUM Element Symbol: Ru Atomic Number: 44
RUTHENIUM Element Symbol: Ru Atomic Number: 44 An initiative of IYC 2011 brought to you by the RACI NICKI BURNS www.raci.org.au RUTHENIUM Element symbol: Ru Atomic number: 44 The element ruthenium is named after Ruthenia. This word is a Latin rendering of the historical territory of Rus, which today is formed with parts of Belarus, Ukraine, western Russia,northeastern Slovakia and eastern Poland. Ruthenium was discovered in 1844 by Karl Karlovitch Klaus, then an unknown professor at the University of Kazan. Klaus could be considered the creator of the chemistry of the platinum metals because of his extensive investigation of rhodium, iridium, osmium, and to a lesser extent, palladium and platinum. Ruthenium is the 74th most abundant metal on Earth and is generally found in ores with the other platinum group metals in the Ural Mountains and in North and South America. Roughly 12 tonnes of ruthenium is mined each year. Ruthenium is also a fission product of235 Uranium, however the extraction from used nuclear fuel is complicated, expensive and also results in radioactive isotopes of ruthenium. Ruthenium has several applications. An alloy containing small amounts of ruthenium with gold increases the stability of gold in jewellery. It is also used in some advanced high-temperature single-crystal superalloys with applications including the turbine blades in jet engines. The “RU” nib in the famous Parker 51 fountain pen was a 14K gold nib tipped with 96.2% ruthenium and 3.8% iridium. 106Ruthenium, a β-decaying isotope, is used in radiotherapy of eye tumours, mainly malignant melanomas of the uvea. -
The Preparation and Characterization of Some Alkanethiolatoosmium Compounds Harold Harris Schobert Iowa State University
Iowa State University Capstones, Theses and Retrospective Theses and Dissertations Dissertations 1970 The preparation and characterization of some alkanethiolatoosmium compounds Harold Harris Schobert Iowa State University Follow this and additional works at: https://lib.dr.iastate.edu/rtd Part of the Inorganic Chemistry Commons Recommended Citation Schobert, Harold Harris, "The preparation and characterization of some alkanethiolatoosmium compounds " (1970). Retrospective Theses and Dissertations. 4357. https://lib.dr.iastate.edu/rtd/4357 This Dissertation is brought to you for free and open access by the Iowa State University Capstones, Theses and Dissertations at Iowa State University Digital Repository. It has been accepted for inclusion in Retrospective Theses and Dissertations by an authorized administrator of Iowa State University Digital Repository. For more information, please contact [email protected]. 71-14,258 SCHOBERT, Harold Harris, 1943- THE PREPARATION AND CHARACTERIZATION OF SOME ALKANETHIOLATOOSMIUM COMPOUNDS. Iowa State University, Ph.D., 1970 Chemistry, inorganic University Microfilms, A XEROX Company, Ann Arbor, Michigan THIS DISSERTATION HAS BEEH MICROFILMED EXACTLY AS RECEIVED THE PREPARATION AND CHARACTERIZATION OF SOME ALKANETHIOLATOOSMIUM COMPOUNDS by Harold Harris Schobert A Dissertation Submitted to the Graduate Faculty in Partial Fulfillment of The Requirements for the Degree of DOCTOR OF PHILOSOPHY Major Subject: Inorganic Chemistry Approved: Signature was redacted for privacy. Signature was redacted for -
Radiation Safety: New International Standards
FEATURES Radiation safety: New international standards The forthcoming International Basic Safety Standards for Protection Against Ionizing Radiation and for the Safety of Radiation Sources are the product of unprecedented co-operation by Abel J. B*y the end of the 1980s, a vast amount of new This article highlights an important result of Gonzalez information had accumulated to prompt a new this work for the international harmonization of look at the standards governing protection radiation safety: specifically, it presents an over- against exposures to ionizing radiation and the view of the forthcoming International Basic safety of radiation sources. Safety Standards for Protection Against Ionizing First and foremost, a re-evaluation of the Radiation and for the Safety of Radiation Sour- radioepidemiological findings from Hiroshima ces — the so-called BSS. They have been jointly and Nagasaki suggested that exposure to low- developed by six organizations — the Food and level radiation was riskier than previously es- Agriculture Organization of the United Nations timated. (FAO), the International Atomic Energy Agency Other developments — notably the nuclear (IAEA), the International Labour Organization accidents at Three Mile Island in 1979 and at (ILO), the Nuclear Energy Agency of the Or- Chernobyl in 1986 with its unprecedented ganization for Economic Co-operation and transboundary contamination — had a great ef- Development (NEA/OECD), the Pan American fect on the public perception of the potential Health Organization (PAHO), and the World danger from radiation exposure. Accidents with Health Organization (WHO). radiation sources used in medicine and industry also have attracted widespread public attention: Cuidad Juarez (Mexico), Mohamadia (Moroc- The framework for harmonization co), Goiania (Brazil), San Salvador (El Sal- vador), and Zaragoza (Spain) are names that ap- In 1991, within the framework of the Inter- peared in the news after people were injured in agency Committee on Radiation Safety, the six radiation accidents.