Radiopharmacy Introduction
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Submission to the Nuclear Power Debate Personal Details Kept Confidential
Submission to the Nuclear power debate Personal details kept confidential __________________________________________________________________________________________ Firstly I wish to say I have very little experience in nuclear energy but am well versed in the renewable energy one. What we need is a sound rational debate on the future energy requirements of Australia. The calls for cessation of nuclear investigations even before a debate begins clearly shows that emotion rather than facts are playing a part in trying to stop the debate. Future energy needs must be compliant to a sound strategy of consistent, persistent energy supply. This cannot come from wind or solar. Lets say for example a large blocking high pressure weather system sits over the Victorian, NSW land masses in late summer- autumn season. We will see low winds for anything up to a week, can the energy market from the other states support the energy needs of these states without coal or gas? I think not. France has a large investment in nuclear energy and charges their citizens around half as much for it than Germany. Sceptics complain about the costs of storage of waste, they do not suggest what is going to happen to all the costs to the environment when renewing of derelict solar panels and wind turbine infrastructure which is already reaching its use by dates. Sceptics also talk about the dangers of nuclear energy using Chernobyl, Three Mile Island and Fuklushima as examples. My goodness given that same rationale then we should have banned flight after the first plane accident or cars after the first car accident. -
HISTORY Nuclear Medicine Begins with a Boa Constrictor
HISTORY Nuclear Medicine Begins with a Boa Constrictor Marshal! Brucer J Nucl Med 19: 581-598, 1978 In the beginning, a boa constrictor defecated in and then analyzed the insoluble precipitate. Just as London and the subsequent development of nuclear he suspected, it was almost pure (90.16%) uric medicine was inevitable. It took a little time, but the acid. As a thorough scientist he also determined the 139-yr chain of cause and effect that followed was "proportional number" of 37.5 for urea. ("Propor inexorable (7). tional" or "equivalent" weight was the current termi One June week in 1815 an exotic animal exhibi nology for what we now call "atomic weight.") This tion was held on the Strand in London. A young 37.5 would be used by Friedrich Woehler in his "animal chemist" named William Prout (we would famous 1828 paper on the synthesis of urea. Thus now call him a clinical pathologist) attended this Prout, already the father of clinical pathology, be scientific event of the year. While he was viewing a came the grandfather of organic chemistry. boa constrictor recently captured in South America, [Prout was also the first man to use iodine (2 yr the animal defecated and Prout was amazed by what after its discovery in 1814) in the treatment of thy he saw. The physiological incident was common roid goiter. He considered his greatest success the place, but he was the only person alive who could discovery of muriatic acid, inorganic HC1, in human recognize the material. Just a year earlier he had gastric juice. -
The Supply of Medical Isotopes
The Supply of Medical Isotopes AN ECONOMIC DIAGNOSIS AND POSSIBLE SOLUTIONS The Supply of Medical Isotopes AN ECONOMIC DIAGNOSIS AND POSSIBLE SOLUTIONS The Supply of Medical Isotopes AN ECONOMIC DIAGNOSIS AND POSSIBLE SOLUTIONS This work is published under the responsibility of the Secretary-General of the OECD. The opinions expressed and arguments employed herein do not necessarily reflect the official views of OECD member countries. This document, as well as any data and any map included herein, are without prejudice to the status of or sovereignty over any territory, to the delimitation of international frontiers and boundaries and to the name of any territory, city or area. Please cite this publication as: OECD/NEA (2019), The Supply of Medical Isotopes: An Economic Diagnosis and Possible Solutions, OECD Publishing, Paris, https://doi.org/10.1787/9b326195-en. ISBN 978-92-64-94550-0 (print) ISBN 978-92-64-62509-9 (pdf) The statistical data for Israel are supplied by and under the responsibility of the relevant Israeli authorities. The use of such data by the OECD is without prejudice to the status of the Golan Heights, East Jerusalem and Israeli settlements in the West Bank under the terms of international law. Photo credits: Cover © Yok_onepiece/Shutterstock.com. Corrigenda to OECD publications may be found on line at: www.oecd.org/about/publishing/corrigenda.htm. © OECD 2019 You can copy, download or print OECD content for your own use, and you can include excerpts from OECD publications, databases and multimedia products in your own documents, presentations, blogs, websites and teaching materials, provided that suitable acknowledgement of OECD as source and copyright owner is given. -
Radioactive Waste
Radioactive Waste 07/05/2011 1 Regulations 2 Regulations 1. Nuclear Regulatory Commission (NRC) 10 CFR 20 Subpart K. Various approved options for radioactive waste disposal. (See also Appendix F) 10 CFR 35.92. Decay in storage of medically used byproduct material. 10 CFR 60. Disposal of high-level wastes in geologic repositories. 10 CFR 61. Shallow land disposal of low level waste. 10 CFR 62. Criteria and procedures for emergency access to non-Federal and regional low-level waste disposal facilities. 10 CFR 63. Disposal of high-level rad waste at Yucca Mountain, NV 10 CFR 71 Subpart H. Quality assurance for waste packaging and transportation. 10 CFR 72. High level waste storage at an MRS 3 Regulations 2. Department of Energy (DOE) DOE Order 435.1 Radioactive Waste Management. General Requirements regarding radioactive waste. 10 CFR 960. General Guidelines for the Recommendation of Sites for the Nuclear Waste Repositories. Site selection guidelines for a waste repository. The following are not regulations but they provide guidance regarding the implementation of DOE Order 435.1: DOE Manual 435.1-1. Radioactive Waste Management Manual. Describes the requirements and establishes specific responsibilities for implementing DOE O 435.1. DOE Guide 435.1-1. Suggestions and acceptable ways of implementing DOE M 435.1-1 4 Regulations 3. Environmental Protection Agency 40 CFR 191. Environmental Standards for the Disposal of Spent Nuclear Fuel, High-level and Transuranic Radioactive Wastes. Protection for the public over the next 10,000 years from the disposal of high-level and transuranic wastes. 4. Department of Transportation 49 CFR Parts 171 to 177. -
Fission-Produced 99Mo Without a Nuclear Reactor
BRIEF COMMUNICATIONS Fission-Produced 99Mo Without a Nuclear Reactor Amanda J. Youker, Sergey D. Chemerisov, Peter Tkac, Michael Kalensky, Thad A. Heltemes, David A. Rotsch, George F. Vandegrift, John F. Krebs, Vakho Makarashvili, and Dominique C. Stepinski Argonne National Laboratory, Nuclear Engineering Division, Argonne, Illinois halted in the past due to inclement weather, natural phenomena, 99Mo, the parent of the widely used medical isotope 99mTc, is cur- flight delays, and terrorist threats (6). rently produced by irradiation of enriched uranium in nuclear reac- The predominant global 99Mo production route is irradiation of tors. The supply of this isotope is encumbered by the aging of these highly enriched uranium (HEU, $20% 235U) solid targets in nuclear reactors and concerns about international transportation and nu- reactors fueled by uranium (2). Other potential 99Mo production Methods: clear proliferation. We report results for the production paths include (n,g)98Mo and (g,n)100Mo; however, both routes re- of 99Mo from the accelerator-driven subcritical fission of an aqueous quire enriched molybdenum material and produce low-specific- solution containing low enriched uranium. The predominately fast 99 neutrons generated by impinging high-energy electrons onto a tan- activity Mo, which cannot be loaded directly on a commercial 99m talum convertor are moderated to thermal energies to increase fission Tc generator. The U.S. National Nuclear Security Administra- processes. The separation, recovery, and purification of 99Mo were tion implements the long-standing U.S. policy to minimize and demonstrated using a recycled uranyl sulfate solution. Conclusion: eliminate HEU in civilian applications by working to convert re- The 99Mo yield and purity were found to be unaffected by reuse of the search reactors and medical isotope production facilities to low previously irradiated and processed uranyl sulfate solution. -
III.2. POSITRON EMISSION TOMOGRAPHY – a NEW TECHNOLOGY in the NUCLEAR MEDICINE IMAGE DIAGNOSTICS (Short Review)
III.2. POSITRON EMISSION TOMOGRAPHY – A NEW TECHNOLOGY IN THE NUCLEAR MEDICINE IMAGE DIAGNOSTICS (Short review) Piperkova E, Georgiev R Dept.of Nuclear Medicine and Dept of Radiotherapy, National Oncological Centre Hospital, Sofia Positron Emission Tomography (PET) is a technology which makes fast advance in the field of Nuclear Medicine. It is different from the X-ray Computed Tomography and Magnetic Resonance Imaging (MRI), where mostly anatomical structures are shown and their functioning could be evaluated only indirectly. In addition, PET can visualise the biological nature and metabolite activity of the cells and tissues. It also has the capability for quantitative determination of the biochemical, physiological and pathological process in the human body (1). The spatial resolution of PET is usually 4-5mm and when the concentration of the positron emitter in the cells is high enough, it allows to see small size pathological zones with high proliferative and metabolite activity ( 3, 7, 17). Following fast and continuous improvement, PET imaging systems have advanced from the Bismuth Germanate Oxide (BGO) circular detector technology to the modern Lutetium Orthosilicate (LSO) and Gadolinium Orthosilicate (GSO) detectors (2, 7, 16). On the other hand, the construction technology has undergone significant progress in the development of new combined PET-CT and PET-MRI systems which currently replace the conventional PET systems with integrated transmission and emission detecting procedures, shown in Fig. 1. Fig. 1 A modern PET-CT system with one gantry. The sensitivity and the accuracy of PET based methods are found to be considerably higher compared to the other existing imaging methods and they can achieve 90-100% in the localisation of different oncological lesions (4, 11, 13, 14). -
Positron Emission Tomography
Positron emission tomography A.M.J. Paans Department of Nuclear Medicine & Molecular Imaging, University Medical Center Groningen, The Netherlands Abstract Positron Emission Tomography (PET) is a method for measuring biochemical and physiological processes in vivo in a quantitative way by using radiopharmaceuticals labelled with positron emitting radionuclides such as 11C, 13N, 15O and 18F and by measuring the annihilation radiation using a coincidence technique. This includes also the measurement of the pharmacokinetics of labelled drugs and the measurement of the effects of drugs on metabolism. Also deviations of normal metabolism can be measured and insight into biological processes responsible for diseases can be obtained. At present the combined PET/CT scanner is the most frequently used scanner for whole-body scanning in the field of oncology. 1 Introduction The idea of in vivo measurement of biological and/or biochemical processes was already envisaged in the 1930s when the first artificially produced radionuclides of the biological important elements carbon, nitrogen and oxygen, which decay under emission of externally detectable radiation, were discovered with help of the then recently developed cyclotron. These radionuclides decay by pure positron emission and the annihilation of positron and electron results in two 511 keV γ-quanta under a relative angle of 180o which are measured in coincidence. This idea of Positron Emission Tomography (PET) could only be realized when the inorganic scintillation detectors for the detection of γ-radiation, the electronics for coincidence measurements, and the computer capacity for data acquisition and image reconstruction became available. For this reason the technical development of PET as a functional in vivo imaging discipline started approximately 30 years ago. -
Radiation Protection Guidelines for Safe Handling of Decedents
Radiation Protection Radiation Protection Guidelines for Safe Handling of Decedents REGDOC-2.7.3 June 2018 Radiation Protection Guidelines for Safe Handling of Decedents Regulatory document REGDOC-2.7.3 © Canadian Nuclear Safety Commission (CNSC) 2018 Cat. No. CC172-195/2018E-PDF ISBN 978-0-660-26930-6 Extracts from this document may be reproduced for individual use without permission provided the source is fully acknowledged. However, reproduction in whole or in part for purposes of resale or redistribution requires prior written permission from the Canadian Nuclear Safety Commission. Également publié en français sous le titre : Lignes directrices sur la radioprotection pour la manipulation sécuritaire des dépouilles Document availability This document can be viewed on the CNSC website. To request a copy of the document in English or French, please contact: Canadian Nuclear Safety Commission 280 Slater Street P.O. Box 1046, Station B Ottawa, ON K1P 5S9 CANADA Tel.: 613-995-5894 or 1-800-668-5284 (in Canada only) Fax: 613-995-5086 Email: [email protected] Website: nuclearsafety.gc.ca Facebook: facebook.com/CanadianNuclearSafetyCommission YouTube: youtube.com/cnscccsn Twitter: @CNSC_CCSN LinkedIn: linkedin.com/company/cnsc-ccsn Publishing history June 2018 Version 1.0 June 2018 REGDOC-2.7.3, Radiation Protection Guidelines for Safe Handling of Decedents Preface This regulatory document is part of the CNSC’s radiation protection series of regulatory documents. The full list of regulatory document series is included at the end of this document and can also be found on the CNSC’s website. Many medical procedures using nuclear substances are carried out to diagnose and treat diseases. -
Toxicological Profile for Plutonium
PLUTONIUM A-1 APPENDIX A. ATSDR MINIMAL RISK LEVELS AND WORKSHEETS The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) [42 U.S.C. 9601 et seq.], as amended by the Superfund Amendments and Reauthorization Act (SARA) [Pub. L. 99– 499], requires that the Agency for Toxic Substances and Disease Registry (ATSDR) develop jointly with the U.S. Environmental Protection Agency (EPA), in order of priority, a list of hazardous substances most commonly found at facilities on the CERCLA National Priorities List (NPL); prepare toxicological profiles for each substance included on the priority list of hazardous substances; and assure the initiation of a research program to fill identified data needs associated with the substances. The toxicological profiles include an examination, summary, and interpretation of available toxicological information and epidemiologic evaluations of a hazardous substance. During the development of toxicological profiles, Minimal Risk Levels (MRLs) are derived when reliable and sufficient data exist to identify the target organ(s) of effect or the most sensitive health effect(s) for a specific duration for a given route of exposure. An MRL is an estimate of the daily human exposure to a hazardous substance that is likely to be without appreciable risk of adverse noncancer health effects over a specified duration of exposure. MRLs are based on noncancer health effects only and are not based on a consideration of cancer effects. These substance-specific estimates, which are intended to serve as screening levels, are used by ATSDR health assessors to identify contaminants and potential health effects that may be of concern at hazardous waste sites. -
Background Radiation and Man-Made and Sources of Radiation
IVITMM r NATIONAL WORKSHOP ON RADIATION PROTECTION AND WASTE MANAGEMENT 17 - 21 MARCH, 1997 Organized By FEDERAL RADIATION PROTECTION SERVICE, IBADAN and NATIONAL AGENCY FOR FOOD AND DRUG ADMINISTRATION AND CONTROL (NAFDAC), ABUJA at the FEDERAL RADIATION PROTECTION SERVICE Department of Physics University of Ibadan, Nigeria TOPIC: BACKGROUND RADIATION AND MAN - MADE AND SOUCES OF RADIATION By Professor Ayo Babalola Federal Radiation Protection Service, Department of Physics, University of Ibadan, Nigeria 3 0-28 L 2. I. Introduction There is a history of up to 50 years of the development of man's use of the atom, and today this industry can be considered as matured technology. However the benefits that have resulted from the use of the atom are not without consequences which are of concern. For few topics have commanded as much attention from all quarters (scientists governments and the general public) as the management of the use of the atom. Ionizing radiation which results from the breaking of the atom is a form of energy, and on account of its ionisation effects, it constitutes hazard to all biological systems, hence the general concern. This concern is born-out of the fact that ionising radiation release (without control) is more potent than the hurricane or earthquake, whose passage is only known by the effects they leave behind. In our discussion of the sources of ionising radiation that are man made, we have to identify the human - needs that led to this peculiar venture which ironically is now viewed in same way as the opening of the pandora box. -
Medical Sources of Radiation
Medical Sources of Radiation Professional Training Programs Oak Ridge Associated Universities Objectives To review the most common uses of radiation in medicine. To discuss new uses for radiation in medicine. To review pertinent regulatory issues. 2 Introduction Medical exposure to an average American is about 3 mSv/yrmSv/yr (300 mrem/yr),mrem/yr), or about 48% of the total average exposure of 620 mremmrem.. Medical exposure to radiation is the largest contributor to our annual average exposure from manman--mademade sources. 3 NCRP Report 160 4 Introduction People are intentionally and purposefully irradiated during medical radiological procedures, which is something that is usually avoided in all other applications using radiation. 5 Introduction The goal in medicine is to minimize risk (keep doses low), without compromising the benefit of the procedure (diagnosis or treatment). 6 Introduction Radiation dose to patients is not regulated. Radiation doses per procedure are decreasing (with a few exceptions), but more procedures are being performed. 7 Introduction There are traditionally three branches of medicine that use ionizing radiation. – Diagnostic Imaging – Nuclear medicine – Radiation therapy 8 Diagnostic Imaging Diagnostic X-X-RayRay Fluoroscopy Mammography Bone Densitometry Computed Tomography Special Procedures Cardiac Cath Lab 9 Diagnostic Imaging MRI and ultrasound procedures do not use ionizing radiation, so will not be discussed. 10 Diagnostic Imaging People who have had xx--rayray procedures or CT scans have been exposed to ionizing radiation, but are not radioactive. 11 Diagnostic Imaging The states regulate the users of x-x-rayray equipment, the FDA regulates the manufacture of x-x-rayray equipment. 12 Diagnostic Imaging 13 Diagnostic Imaging 14 Diagnostic Imaging 15 Diagnostic Imaging 16 Nuclear Medicine The patient is purposefully administered radioactive material, and becomes the source of radiation. -
Radiation Protection Guides
[Year] Rad iation Protection Guide For Medical Use of Radioactive Materials & Radiation Producing Machines EHS Radiation Safety 122 Grand Ave. Ct. Ph. 319-335-8501 March 2009 The University of Iowa prohibits discrimination in employment and in its educational programs and activities on the basis of race, national origin, color, creed, religion, sex, age, disability, veteran status, sexual orientation, gender identity, or associational preference. The University also affirms its commitment to providing equal opportunities and equal access to University facilities. For additional information on nondiscrimination policies, contact the Coordinator of Title IX, Section 504, and the ADA in the Office of Affirmative Action, (319) 335-0705 (voice) or (319) 335-0697 (text), 202 Jessup Hall, The University of Iowa, Iowa City, Iowa, 52242- 1316. PREFACE The University of Iowa is committed to providing its patients, visitors, students and employees with an environment where sources of radiation are used safely for the purposes of medicine, research and teaching. Attainment of this goal requires the cooperation and commitment of all persons involved. The Environmental Health & Safety (formerly Health Protection Office) is responsible for implementing the University’s radiation safety program as defined by its Radiation Safety Committees, broadscope license, and state and federal regulations. Department heads, faculty members, supervisors and individual users are directly responsible for maintaining an environment that promotes compliance with these