Diagnostic Imaging; Nuclear Medicine; Radiation Risk Vs. Benefit
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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. -
Radiopharmacy Introduction
Radiopharmacy Introduction This Chapter is an amended version of the Good Radiopharmacy Practice Position Paper (GRPP), prepared as a policy document by the SIG Radiopharmacy and Nuclear Medicine of the Netherlands Association of Hospital Pharmacists (NVZA). Introduction In practice, Healthcare Inspectorate (IGZ) inspections in hospitals identify issues during the preparation and reconstitution and/ or aseptic handling (RAH) of radiopharmaceuticals in relation to the interpretation and application of the Dutch Good Manufacturing Practice for hospitals (GMP-z) guidelines. This Chapter aims to provide an unambiguous framework to ensure that there is no doubt about the guidelines and circumstances that apply to every situation. Principles, legislation and regulations In the Netherlands, around 65 hospitals have a Nuclear Medicine Department. More than 50% of these Departments are currently supplied by one of the three radiopharmacies of GE Healthcare. In the other hospitals, the radiopharmaceuticals are prepared by the Radiopharmacy, as well known as the “hot lab”. As this generally concerns centers with a major Nuclear Medicine Department, it can be said that the largest volume of radiopharmaceuticals is produced in the hospitals themselves. Radionuclides and radiopharmaceuticals are also purchased ready-made and are prepared for administration by the hot lab. Radiopharmaceuticals are ordinary pharmacy preparations, but differ from other prepared medicines due to their small-scale preparation (always prepared shortly before for administration (PFA)) on a patients name, sometimes preceded by a labelling step with a radionuclide generated in-house or not), their short shelf-life (due to radioactive decay) and the low pharmacological doses that are generally used. The radiation dose for the patient is generally low, as most radiopharmaceuticals are used for diagnostic purposes. -
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. -
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. -
Mean Glandular Dose from Routine Mammography
Naresuan University Journal 2006; 14(3): 19-26 19 Mean Glandular Dose from Routine Mammography Supawitoo Sookpenga,* and Potjana Kettedb a Department of Radiological Technology, Faculty of Allied Health Science, Naresuan University, Phitsanulok 65000, Thailand. b Department of Radiology, Buddhachinaraj Hospital, Phitsanulok 65000, Thailand. *Corresponding author. E-mail address: [email protected] (S. Sookpeng) Received 21 July 2006; accepted 6 December 2006 Abstract A mammography examination facilitates the early detection of breast cancer. However, the potential risk of radiation-induced carcinogenesis is also increased with such a procedure. The objective of this research was to measure the mean glandular dose (MGD) from craniocaudal (CC) and mediolateral oblique (MLO) views in each breast and the total dose per woman (for both breasts and two views) from the exposure factor in patients undergoing mammography on six mammography x-ray generators in the lower region of northern Thailand. The values of compressed breast thickness (CBT), as well as the MGD calculated from the exposure and tube voltage both mAs and target/filter combination, were collected from 2,060 films from 515 women ranging in age from 28 to 91 years. Significant differences were found between MGD from CC and MLO projections. The MGD per film was 1.42+0.80 mGy for the CC projection and 1.56+0.86 mGy for the MLO projection, (p<0.001). The MGD per CC and MLO film was significantly related to CBT (r = 0.610, p<0.01 and r = 0.596, p<0.01 respectively). The result indicated that 96.1 % of CC films and 94.2 % of MLO films had doses less than 3.0 mGy as recommended by the American College of Radiology recommendations. -
Radiation Protection of the Public S15 Oral Presentations
Contents Session 15: Radiation protection of the public S15 Oral presentations S15-01 The main directions of the Russian efforts in radiation safety and health protection . 2180 Kiselev, Mikhail; Shandala, Nataliya S15-02 Spanish national campaign for the search and recovery of orphan radioactive sources . 2189 Carboneras, Pedro; Ortiz, Maria Teresa; Rueda, Carmen S15-03 Mitigation of exposure to radon by household water treatment . 2200 Turtiainen, Tuukka S15-04 Dose assessment for tritium releases during normal operation of NPP (ABSTRACT) . 2207 Duran, Juraj; Malátová, Irena S15-05 The legacy of uranium mines – Pluralist Expertise Group experiment on uranium mines in Limousin (France) (ABSTRACT) . 2208 Ringeard, Caroline; Catelinois, Olivier; Sene, Monique; Barbey, Pierre; Andres, Christian; Devin, Patrick; Vandenhove, Hildegarde; Servant-Perrier, Anne-Christine; Leuraud, Klervi; Zerbib, Jean-Claude Third European IRPA Congress 2010, Helsinki, Finland Contents Topic 15: Radiation protection of the public P15 Poster presentations P15-01 Radiation situation in Moscow and public doses due to man-made radiation exposure . 2210 Metlyaev, Evgeny; Filonova, Anna P15-02 Ionizing radiation exposure of the Belgian population in 2006 . 2216 Vanmarcke, Hans; Bosmans, Hilde; Eggermont, Gilbert P15-03 Sharing an environmental monitoring network: The AREVA Tricastin experience . 2226 Mercat, Catherine; Devin, Patrick; Garnier, François P15-04 137Cs activity concentrations in Polish meats – Current status and dose assessment for consumers . 2236 Rachubik, Jarosław P15-05 Public doses due to tritium emissions from Cernavoda NPP (ABSTRACT) . 2244 Bobric, Elena; Popescu, Ion; Simionov, Vasile P15-06 New Swedish regulations for clearance of materials, rooms, buildings and land . 2245 Efraimsson, Henrik P15-07 The approach to assessing doses to humans in the Posiva safety case . -
Validation of Mean Glandular Dose Values Provided by a Digital Breast Tomosynthesis System in Brazil
ISSSD 2014 April 13 to 16th, 2014. Cusco, Peru VALIDATION OF MEAN GLANDULAR DOSE VALUES PROVIDED BY A DIGITAL BREAST TOMOSYNTHESIS SYSTEM IN BRAZIL Bruno Beraldo Oliveira1, Lucas Paixão1, Sabrina Donato da Silva1 Maria Helena Araújo Teixeira2, Maria do Socorro Nogueira1/3 1 Post-graduation in Sciences and Technology of Radiations Minerals and Materials - CDTN/CNEN Presidente Antônio Carlos, 6627 31270-901, Belo Horizonte, Brazil [email protected] 2 Dr Maria Helena Araújo Teixeira Clinic Guajajaras, 40 30180-100, Belo Horizonte, Brazil [email protected] 3 Development Center of Nuclear Technology - CDTN/CNEN Presidente Antônio Carlos, 6627 31270-901, Belo Horizonte, Brazil [email protected] 213 ISSSD 2014 April 13 to 16th, 2014. Cusco, Peru Abstract Digital breast tomosynthesis (DBT) is an emerging imaging modality that provides quasi-three-dimensional structural information of the breast and has strong promise to improve the differentiation of normal tissue and suspicious masses reducing the tissue overlaps. DBT images are reconstructed from a sequence of low-dose X-ray projections of the breast acquired at a small number of angles over a limited angular range. The Hologic Selenia Dimensions system is equipped with an amorphous Selenium (a-Se) detector layer of 250 μm thickness and a 70 μm pixel pitch. Studies are needed to determine the radiation dose of patients that are undergoing this emerging procedure to compare with the results obtained in DBT images. The mean glandular dose (DG) is the dosimetric quantity used in quality control of the mammographic systems. The aim of this work is to validate DG values for different breast thicknesses provided by a Hologic Selenia Dimensions system using a DBT mode in comparison with the same results obtained by a calibrated 90X5-6M-model Radcal ionization chamber.