Radioisotope X-Ray Fluorescence Spectrometry

Total Page:16

File Type:pdf, Size:1020Kb

Radioisotope X-Ray Fluorescence Spectrometry TECHNICAL REPORTS SERIES No. 115 Radioisotope X-Ray Fluorescence Spectrometry INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA,1970 RADIOISOTOPE X-RAY FLUORESCENCE SPECTROMETRY The following States jre Members of the International Atomic Energy Agency: AFGHANISTAN GREECE NORWAY ALBANIA GUATEMALA PAKISTAN ALGERIA HAITI PANAMA ARGENTINA HOLY SEE PARAGUAY AUSTRALIA HUNGARY PERU AUSTRIA ICELAND PHILIPPINES BELGIUM INDIA POLAND BOLIVIA INDONESIA PORTUGAL BRAZIL IRAN ROMANIA BULGARIA IRAQ SAUDI ARABIA BURMA IRELAND SENEGAL BYELORUSSIAN SOVIET ISRAEL SIERRA LEONE SOCIALIST REPUBLIC ITALY SINGAPORE CAMBODIA IVORY COAST SOUTH AFRICA CAMEROON JAMAICA SPAIN CANADA JAPAN SUDAN CEYLON JORDAN SWEDEN CHILE KENYA SWITZERLAND CHINA KOREA, REPUBLIC OF SYRIAN ARAB REPUBLIC COLOMBIA KUWAIT THAILAND CONGO, DEMOCRATIC LEBANON TUNISIA REPUBLIC OF LIBERIA TURKEY COSTA RICA LIBYAN ARAB REPUBUC UGANDA CUBA LIECHTENSTEIN UKRAINIAN SOVIET SOCIALIST CYPRUS LUXEMBOURG REPUBLIC CZECHOSLOVAK SOCIALIST MADAGASCAR UNION OF SOVIET SOCIALIST REPUBLIC MALAYSIA REPUBLICS DENMARK MALI UNITED ARAB REPUBLIC DOMINICAN REPUBLIC MEXICO UNITED KINGDOM OF GREAT ECUADOR MONACO BRITAIN AND NORTHERN EL SALVADOR MOROCCO IRELAND ETHIOPIA NETHERLANDS UNITED STATES OF AMERICA FINLAND NEW ZEALAND URUGUAY FRANCE NICARAGUA VENEZUELA GABON NIGER VIET-NAM GERMANY, FEDERAL REPUBLIC OF NIGERIA YUGOSLAVIA GHANA ZAMBIA The Agency's Statute was approved on 23 October 1956 by the Conference on the Statute of the IAEA held at United Nations Headquarters, New York; it entered into force on 29 July 1957. The Headquarters of the Agency are situated in Vienna. Its principal objective is "to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world". © IAEA, 1970 Permission to reproduce or translate the information contained in this publication may be obtained by writing to the International Atomic Energy Agency, Kamtner Ring 11, P.O. Box 590, A-1011 Vienna, Austria. Printed by the IAEA in Austria June 1970 TECHNICAL REPORTS SERIES No. 115 RADIOISOTOPE X-RAY FLUORESCENCE SPECTROMETRY REPORT OF A PANEL HELD IN VIENNA, 13 - 17 MAY 1968 INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 1970 RADIOISOTOPE X-RAY FLUORESCENCE-SPECTROMETRY IAEA, VIENNA, 1970 STI/DOC/10/115 FOREWORD Radioisotope X-ray fluorescence is one of the more recent techniques developed as a result of the general availability of sealed radioisotope sources. It is mainly used for non-destructive elemental analysis and for the measure- ment of coating thickness. In both these applications it has become comple- mentary to, and competitive with, several older-established methods. A great variety of portable equipment for the analysis of alloys, both in industrial plant laboratories and in the field, now uses radioisotope X-ray fluorescence techniques as a basic element in its design. This equipment is in wide use in geophysical prospecting and in mine development and control. Also important in mining is the development of borehole probes for use in percussion-drilled holes; this is an attractive alternative to the analysis of drill cores. On-line equipment incorporating these techniques has been developed for use in mineral processing plants, especially for analysis of lead, zinc, tin, copper, iron, calcium and silicon. Although industry was slow to intro- duce this on-line application, several commercial installations are now reported to be in operation. For on-line measurement in particular, the combination of radioisotope X-ray fluorescence with neutron activation analysis (using radioisotope neutron sources) is now being developed. This will be especially useful where several elements have to be analysed simultaneously. Commercial equipment, designed for use in computer-control systems, is now available for regulating the thickness of coatings in the tinning and galvanizing processes. An important development is the work on low-Z analysis by alpha excitation. This method of analysis can now be seriously considered for industrial application, especially since an intrinsically safe alpha source, 242Cm, has recently become available commercially. Also important in ex- tending the range of applications is the development of solid-state detectors, particularly the Si(Li) type, with which inter-element effects can be reduced and limits of detection can be lowered; a main reason for the improvement here is that balanced X-ray filters are not required. The two problems limiting higher accuracy are those of inter-element effects — already largely solved — and of particle-size effects. Many experts are confident that present work aimed at overcoming particle-size effects will be successful. Although development work is proceeding in many directions, there is a wide range of possible uses that have as yet been barely explored. The Panel whose findings are reported here met in Vienna on 13—17 May 1968. Its task was to review current techniques and applications, to comment on the factors that limit performance, and to consider promising lines of development and extensions of present usage. The report is based on Panel discussions and on written contributions from each Panel Member, as well as on a paper by B. Dziunikowski, Institute of Radioisotope Techniques, Academy of Mining and Metallurgy, Cracow, Poland. The International Atomic Energy Agency is greatly indebted to C. G. Clayton, Chairman of the Panel, for compiling and editing the final text of the report and ensuring that the information is up to date. CONTENTS A. GENERAL CONSIDERATIONS . 1 A.l. Comparison between radioisotope X-ray fluorescence and other analytical techniques 1 A.1.1. General comparisons 1 A. 2. Comparison between radioisotope and conventional X-ray fluorescence analysis 4 A. 2.1. Relative performance 4 A.3. Comparison between primary and secondary alpha, beta, gamma and X-ray excitation 6 A.3.1. Principal characteristics of the different methods of excitation 6 A.3.2. Choice of source 9 A. 3.3. Comparison of the available excitation sources 15 A.3.4. A comment on proton excitation 16 A.4. Present status of the theory of radioisotope X-ray fluorescence 16 B. INSTRUMENTATION AND TECHNIQUES 19 B.l. Components of radioisotope X-ray fluorescent analysers 19 B.l.l. Radioactive sources 19 B.l.2. Detectors , 25 B.1.3. Electronic instrumentation 28 B.l.4. Windows 28 B.1.5. X-ray filters for energy selection 29 B.l.6. Cooling systems 30 B.l.7. Multi-element computers 31 B.2. Analytical Instruments and systems 32 B.2.1. Commercially available systems 32 B.2.2. Other systems in use or under development 40 B.3. Techniques for minimizing interference 41 B.3.1. Matrix effects 41 В. 3.2. Heterogeneity effects 42 B.4. Calibration 44 С. APPLICATIONS 45 C.l. Metalliferous mineral exploration and development 45 C.l.l. Unprepared rock surfaces 45 C.l.2. Drill cores 46 C.1.3. Boreholes 47 C.l.4. Particulate samples 47 C.2. On-stream process control 50 C.2.1. Introduction 50 C.2.2. Analysis of slurries 51 C.2.3. Analysis of crushed materials 63 C.2.4. Analysis of solutions 70 C.3. Alloy analysis 70 C.4. Coating thickness measurement 71 C.4.1. Introduction 71 C.4.2. X-ray fluorescence methods of measuring coating thickness 71 C.4.3. Applications 71 C.4.4. Tin coating gauges 71 C.4.5. Zinc coating gauges 77 C.5. Miscellaneous applications 78 C.5.1. Medical 78 C.5.2. Other applications 79 C.6. Health and safety considerations 79 C.6.1. External hazards 79 C.6.2. Internal hazards 80 D. PROSPECTS AND REQUIREMENTS 81 E. RECOMMENDATIONS TO THE AGENCY 83 REFERENCES 85 APPENDIX I — Manufacturers' specification forms 89 APPENDIX II — Classification of preferred terms and definitions relating to radioisotope X-ray fluorescence analysis 99 LIST OF PARTICIPANTS AND SECRETARIAT 101 A. GENERAL CONSIDERATIONS A. 1. COMPARISON BETWEEN RADIOISOTOPE X-RAY FLUORESCENCE AND OTHER ANALYTICAL TECHNIQUES Radioisotope X-ray fluorescence analysis is one of a number of tech- niques now available to determine the concentration of elements in different materials. Its suitability for any application depends on a variety of factors, such as the environment in which the analysis is to be carried out and the limits of detection required. In the present comparison, radioisotope X-ray fluorescence is first examined in a general manner and then compared specifically with conven- tional X-ray fluorescence analysis. A. 1.1. General comparisons (a) Analyses in the laboratory , A general comparison is difficult to make because of the many factors which have to be taken into account, but an attempt has been made to summarize the present situation in Table I. The different analytical techniques have been assigned a figure of merit, i.e. 1, 2, 3, 4 or 5 (1 indicating highest performance and 5 lowest performance) for the particular characteristics defined below. (i) Selectivity This is the ability of the technique to ensure that the signal being measured originates from the element being determined. (ii) Limit of detection This applies to the sample being examined but does not .take into account concentration or dilution factors. (iii) Accuracy This refers to the degree of correctness with which a method of measurement yields the true value of the quantity being measured. (iv) Equipment cost . This is the cost of all the equipment required to complete an analysis. 1 TABLE I. COMPARISON BETWEEN THE LABORATORY APPLICATION OF RADIOISOTOPE X-RAY FLUORESCENCE AND THAT OF OTHER ANALYTICAL TECHNIQUES Limit of Equipment Laboratory Technique Selectivity Accuracy detection cost cost Atomic absorption 1 1 3 2 2 Atomic fluorescence 1 1 3 2 2 Polarography 4 2 3 2 2 Colorimetric 4 2 3 1 1 Fast neutron 3 4 2 4 4 Radioisotope X.R.F. 3 4 2 2 1 Tube X.R.F. 2 3 1 4 3 Direct reader 2 2 1 3 3 Analytical time Operator time and grade Technique Massive Massive Powders Liquids solids solids Powders Liquids Atomic absorption 4 3 1 3 3 1 Atomic fluorescence 4 3 1 3 3 1 Polarography 5 4 3 4 4 3 Colorimetric 5 4 3 4 4 3 Fast neutron 2 1 2 2 1 2 Radioisotope X.R.F.
Recommended publications
  • Radioisotopes and Radiopharmaceuticals
    RADIOISOTOPES AND RADIOPHARMACEUTICALS Radioisotopes are the unstable form of an element that emits radiation to become a more stable form — they have certain special attributes. These make radioisotopes useful in areas such as medicine, where they are used to develop radiopharmaceuticals, as well as many other industrial applications. THE PRODUCTION OF TECHNETIUM-99m RADIOPHARMACEUTICALS: ONE POSSIBLE ROUTE IRRADIATED U-235 99 TARGETS MO PROCESSING FACILITY HOSPITAL RADIOPHARMACY (MIXING WITH BIOLOGICAL MOLECULES THAT BIND AT DIFFERENT LOCATIONS IN THE 99mTC IS IDEAL FOR DIAGNOSTICS BECAUSE OF BODY, SUPPORTING A WIDE ITS SHORT HALF-LIFE (6 HOURS) AND IDEAL GAMMA EMISSION RANGE OF MEDICAL NUCLEAR APPLICATIONS) REACTOR: 6 HOURS MAKES DISTRIBUTION DIFFICULT 99MO BULK LIQUID TARGET ITS PARENT NUCLIDE, MOLYBDENUM-99, IS PRODUCED; ITS HALF-LIFE (66 HOURS) MAKES 99 99m IRRADIATION IT SUITABLE FOR TRANSPORT MO/ TC GENERATORS 99MO/99mTC GENERATORS ARE PRODUCED AND DISTRIBUTED AROUND THE GLOBE 99MO/99TC GENERATOR MANUFACTURER Radioisotopes can occur naturally or be produced artificially, mainly in research reactors and accelerators. They are used in various fields, including nuclear medicine, where radiopharmaceuticals play a major role. Radiopharmaceuticals are substances that contain a radioisotope, and have properties that make them effective markers in medical diagnostic or therapeutic procedures. The chemical presence of radiopharmaceuticals can relay detailed information to medical professionals that can help in diagnoses and treatments. Eighty percent of all diagnostic medical scans worldwide use 99mTc, and its availability, at present, is dependent on the production of 99Mo in research reactors. Globally, the number of medical procedures involving the use of radioisotopes is growing, with an increasing emphasis on radionuclide therapy using radiopharmaceuticals for the treatment of cancer..
    [Show full text]
  • OPERATIONAL GUIDANCE on HOSPITAL RADIOPHARMACY: a SAFE and EFFECTIVE APPROACH the Following States Are Members of the International Atomic Energy Agency
    OPERATIONAL GUIDANCE ON HOSPITAL RADIOPHARMACY: A SAFE AND EFFECTIVE APPROACH The following States are Members of the International Atomic Energy Agency: AFGHANISTAN GUATEMALA PAKISTAN ALBANIA HAITI PALAU ALGERIA HOLY SEE PANAMA ANGOLA HONDURAS PARAGUAY ARGENTINA HUNGARY PERU ARMENIA ICELAND PHILIPPINES AUSTRALIA INDIA POLAND AUSTRIA INDONESIA PORTUGAL AZERBAIJAN IRAN, ISLAMIC REPUBLIC OF QATAR BANGLADESH IRAQ REPUBLIC OF MOLDOVA BELARUS IRELAND ROMANIA BELGIUM ISRAEL RUSSIAN FEDERATION BELIZE ITALY SAUDI ARABIA BENIN JAMAICA SENEGAL BOLIVIA JAPAN SERBIA BOSNIA AND HERZEGOVINA JORDAN SEYCHELLES BOTSWANA KAZAKHSTAN BRAZIL KENYA SIERRA LEONE BULGARIA KOREA, REPUBLIC OF SINGAPORE BURKINA FASO KUWAIT SLOVAKIA CAMEROON KYRGYZSTAN SLOVENIA CANADA LATVIA SOUTH AFRICA CENTRAL AFRICAN LEBANON SPAIN REPUBLIC LIBERIA SRI LANKA CHAD LIBYAN ARAB JAMAHIRIYA SUDAN CHILE LIECHTENSTEIN SWEDEN CHINA LITHUANIA SWITZERLAND COLOMBIA LUXEMBOURG SYRIAN ARAB REPUBLIC COSTA RICA MADAGASCAR TAJIKISTAN CÔTE D’IVOIRE MALAWI THAILAND CROATIA MALAYSIA THE FORMER YUGOSLAV CUBA MALI REPUBLIC OF MACEDONIA CYPRUS MALTA TUNISIA CZECH REPUBLIC MARSHALL ISLANDS TURKEY DEMOCRATIC REPUBLIC MAURITANIA UGANDA OF THE CONGO MAURITIUS UKRAINE DENMARK MEXICO UNITED ARAB EMIRATES DOMINICAN REPUBLIC MONACO UNITED KINGDOM OF ECUADOR MONGOLIA GREAT BRITAIN AND EGYPT MONTENEGRO NORTHERN IRELAND EL SALVADOR MOROCCO ERITREA MOZAMBIQUE UNITED REPUBLIC ESTONIA MYANMAR OF TANZANIA ETHIOPIA NAMIBIA UNITED STATES OF AMERICA FINLAND NEPAL URUGUAY FRANCE NETHERLANDS UZBEKISTAN GABON NEW ZEALAND VENEZUELA GEORGIA NICARAGUA VIETNAM GERMANY NIGER YEMEN GHANA NIGERIA ZAMBIA GREECE NORWAY ZIMBABWE The Agency’s Statute was approved on 23 October 1956 by the Conference on the Statute of the IAEA held at United Nations Headquarters, New York; it entered into force on 29 July 1957. The Headquarters of the Agency are situated in Vienna.
    [Show full text]
  • Chapter 12 Monographs of 99Mtc Pharmaceuticals 12
    Chapter 12 Monographs of 99mTc Pharmaceuticals 12 12.1 99mTc-Pertechnetate I. Zolle and P.O. Bremer Chemical name Chemical structure Sodium pertechnetate Sodium pertechnetate 99mTc injection (fission) (Ph. Eur.) Technetium Tc 99m pertechnetate injection (USP) 99m ± Pertechnetate anion ( TcO4) 99mTc(VII)-Na-pertechnetate Physical characteristics Commercial products Ec=140.5 keV (IT) 99Mo/99mTc generator: T1/2 =6.02 h GE Healthcare Bristol-Myers Squibb Mallinckrodt/Tyco Preparation Sodium pertechnetate 99mTc is eluted from an approved 99Mo/99mTc generator with ster- ile, isotonic saline. Generator systems differ; therefore, elution should be performed ac- cording to the manual provided by the manufacturer. Aseptic conditions have to be maintained throughout the operation, keeping the elution needle sterile. The total eluted activity and volume are recorded at the time of elution. The resulting 99mTc ac- tivity concentration depends on the elution volume. Sodium pertechnetate 99mTc is a clear, colorless solution for intravenous injection. The pH value is 4.0±8.0 (Ph. Eur.). Description of Eluate 99mTc eluate is described in the European Pharmacopeia in two specific monographs de- pending on the method of preparation of the parent radionuclide 99Mo, which is generally isolated from fission products (Monograph 124) (Council of Europe 2005a), or produced by neutron activation of metallic 98Mo-oxide (Monograph 283) (Council of Europe 2005b). Sodium pertechnetate 99mTc injection solution satisfies the general requirements of parenteral preparations stated in the European Pharmacopeia (Council of Europe 2004). The specific activity of 99mTc-pertechnetate is not stated in the Pharmacopeia; however, it is recommended that the eluate is obtained from a generator that is eluted regularly, 174 12.1 99mTc-Pertechnetate every 24 h.
    [Show full text]
  • An EANM Procedural Guideline
    European Journal of Nuclear Medicine and Molecular Imaging https://doi.org/10.1007/s00259-018-4052-x GUIDELINES Clinical indications, image acquisition and data interpretation for white blood cells and anti-granulocyte monoclonal antibody scintigraphy: an EANM procedural guideline A. Signore1 & F. Jamar2 & O. Israel3 & J. Buscombe4 & J. Martin-Comin5 & E. Lazzeri6 Received: 27 April 2018 /Accepted: 6 May 2018 # The Author(s) 2018 Abstract Introduction Radiolabelled autologous white blood cells (WBC) scintigraphy is being standardized all over the world to ensure high quality, specificity and reproducibility. Similarly, in many European countries radiolabelled anti-granulocyte antibodies (anti-G-mAb) are used instead of WBC with high diagnostic accuracy. The EANM Inflammation & Infection Committee is deeply involved in this process of standardization as a primary goal of the group. Aim The main aim of this guideline is to support and promote good clinical practice despite the complex environment of a national health care system with its ethical, economic and legal aspects that must also be taken into consideration. Method After the standardization of the WBC labelling procedure (already published), a group of experts from the EANM Infection & Inflammation Committee developed and validated these guidelines based on published evidences. Results Here we describe image acquisition protocols, image display procedures and image analyses as well as image interpre- tation criteria for the use of radiolabelled WBC and monoclonal antigranulocyte antibodies. Clinical application for WBC and anti-G-mAb scintigraphy is also described. Conclusions These guidelines should be applied by all nuclear medicine centers in favor of a highly reproducible standardized practice. Keywords Infection .
    [Show full text]
  • Learn More About X-Rays, CT Scans and Mris (Pdf)
    What is the difference between X-Rays, CT Scans, and MRIs? X-Rays are a form of electromagnetic radiation, like light. They are less energetic than gamma rays, and more energetic than ultraviolet light. Because they pass easily through soft tissue, like organs and muscles, but not so easily through hard tissue like bones and teeth, we are most familiar with them being used to look at skeletal structures. Sometimes a person ingests or has injected an X-ray opaque fluid that will fill a space of interest for X-ray imaging. This is called an angiogram. A nuclear scan uses an injected gamma ray emitting substance that accumulates in the organ of interest and a special camera records the gamma rays. A CT Scan is usually a series of X-rays taken from different directions that are then assembled into a three dimensional model of the subject in a computer. CT stands for computed tomography, and tomography means a picture of a slice. Where an X-ray may show edges of soft tissues all stacked on top of each other, the computer in a CT scan can figure out how those edges relate to each other in depth, and so the image has much more soft tissue usability. Another kind of CT scan uses positrons. I have to mention this because positrons are antimatter electrons (Yes, antimatter does exist and it is useful!) In Positon Emission Tomography (PET) a positron emitting radionuclide (radioactive material) is attached to a metabolically useful molecule. This is introduced to the tissue, and as emitted positrons decompose they emit gamma rays which can be traced by the machine and computer back to their points of origin, and an image is formed.
    [Show full text]
  • CEA-Scan Package Insert
    10C007-3 CEA-Scan® (Arcitumomab) 8/99 For the Preparation of Technetium Tc 99m Arcitumomab. Sterile, Non-Pyrogenic, Lyophilized Powder for Intravenous Use Only. DESCRIPTION CEA-Scan® is a radiodiagnostic agent consisting of a murine monoclonal antibody Fab′ fragment, Arcitumomab, formulated to be labeled with Technetium Tc 99m. The active component, Arcitumomab, is a Fab′ fragment generated from IMMU-4, a murine IgG1 monoclonal antibody produced in murine ascitic fluid supplied to Immunomedics, Inc., by Charles River Laboratories. IMMU-4 is purified from the ascitic fluid and is digested with pepsin to produce F(ab′)2 fragments and subsequently reduced to produce the 50,000-dalton Arcitumomab. Each vial contains the non-radioactive materials necessary to prepare one patient dose. CEA-Scan® is a sterile, lyophilized formulation, containing 1.25 mg of Arcitumomab and 0.29 mg stannous chloride per vial, with potassium sodium tartrate tetrahydrate, sodium acetate trihydrate, sodium chloride, acetic acid, glacial, hydrochloric acid, and sucrose. The imaging agent, Technetium Tc 99m CEA-Scan®, Technetium Tc 99m Arcitumomab, is formed by reconstitution of the contents of the CEA-Scan® vial with 30 mCi of Tc 99m sodium pertechnetate in 1 ml of Sodium Chloride for Injection, USP. The resulting solution is pH 5-7 and for intravenous use only. Following administration, the labeled antibody can be visualized by common nuclear medicine instrumentation. Physical Characteristics of Technetium Tc 99m Technetium Tc 99m decays by isomeric transition with a physical half-life of 6.02 hours.2 The principal photon that is useful for detection and imaging is listed in the following table.
    [Show full text]
  • FR H 0356 001 Finalspc.Pdf
    1. NAME OF THE MEDICINAL PRODUCT STAMICIS 1 mg kit for radiopharmaceutical preparation 2. QUALITATIVE AND QUANTITATIVE COMPOSITION Each vial contains 1 mg [Tetrakis (2-methoxyisobutyl isonitrile) copper (I)] tetrafluoroborate. The radionuclide is not part of the kit. Excipients with known effect: One ml of solution contains 4.5 mg of sodium For the full list of excipients, see section 6.1. 3. PHARMACEUTICAL FORM Kit for radiopharmaceutical preparation. White powder. 4. CLINICAL PARTICULARS 4.1. Therapeutic indications This medicinal product is for diagnostic use only. This is indicated for adults. For paediatric population see section 4.2. After radiolabelling with sodium pertechnetate (99mTc) solution, the solution of technetium (99mTc) sestamibi obtained is indicated for: Myocardial perfusion scintigraphy for the detection and localisation of coronary artery disease (angina pectoris and myocardial infarction). Assessment of global ventricular function. First-pass technique for determination of ejection fraction and/or ECG-triggered, gated SPECT for evaluation of left ventricular ejection fraction, volumes and regional wall motion. Scintimammography for the detection of suspected breast cancer when mammography is equivocal, inadequate or indeterminate. Localisation of hyperfunctioning parathyroid tissue in patients with recurrent or persistent disease in both primary and secondary hyperparathyroidism, and in patients with primary hyperparathyroidism scheduled to undergo initial surgery of the parathyroid glands. 4.2 Posology and method of administration Posology Adults and elderly population Posology may vary depending on gamma camera characteristics and reconstruction modalities. The injection of activities greater than local DRLs (Diagnostic Reference Levels) should be justified. 05/2016 1 The recommended activity range for intravenous administration to an adult patient of average weight (70 kg) is for: Diagnosis of reduced coronary perfusion and myocardial infarction 400-900 MBq.
    [Show full text]
  • Releasing Nuclear Medicine Patients to the Public
    Educational Objectives • Introduce participants to the medical conditions that are Releasing Nuclear Medicine treated with radioiodine. • Review the regulatory considerations regarding Patients to the Public: inpatient and outpatient radioiodine procedures. Dose Calculations and Discharge • Review ways in which the regulatory requirements may be satisfied, including “public” radiation dose Instructions computations, content of post-discharge instructions and addressing the concerns of patients and their families. Robert E. Reiman, MD Radiation Safety Division • Introduce Web-based methods to facilitate Duke University Medical Center documentation of outpatient treatment. Durham, NC Medically Useful Iodine Isotopes Treatment of Toxic Goiter Isotope Half-life Primary Use Emissions I-123 13.3 hours γ (0.158 MeV) Diagnosis • Surgery (not done, except for very large thyroid, low iodine uptake, cancer or I-124 4.2 days β+ and γ (0.511 Diagnosis, pregnancy) MeV +) Therapy(?) I-125 59.4 days γ (0.035 MeV) Brachytherapy • Drugs (propylthiouracil) and beta blockers (short-term) I-131 8.0 days β- (0.606 MeV), Diagnosis, • Ablation with radioactive iodine γ (0.364 MeV) Therapy Radioiodine Treatment Thyroid Carcinoma • I-131 sodium iodide solution, orally • 8 – 15 millicuries for diffuse toxic goiter • Incidence: about 3 per 100,000 per year • 15 – 40 millicuries for toxic multinodular • Females > Males (2:1) goiter • About 80% papillary type; remainder • Must know the % uptake at 24 hours to follicular or medullary types. compute administered activity and • Medullary thyroid carcinoma does not clearance rates take up radioiodine. 1 Diagnosis of Thyroid Treatment of Thyroid Carcinoma Carcinoma • Surgical removal of thyroid gland and • Usually asymptomatic except for a dissection of local lymph nodes.
    [Show full text]
  • Nuclide Safety Data Sheet Iodine-131
    131 Nuclide Safety Data Sheet 131 Iodine-131 I www.nchps.org I I. PHYSICAL DATA Radiation: Gammas & X-rays: primary 364 keV (81% abundance); others – 723 keV Betas: primary 606 keV (89% abundance); others 248 – 807 keV 1 Gamma Constant: 0.22 mR/hr per mCi @ 1.0 meter [7.647E-5 mSv/hr per MBq @ 1.0 meter] Half-Life [T½] : Physical T½: 8.04 days Biological T½: 120-138 days (unbound iodine) Effective T½: 7.6 days (unbound iodine) Specific Activity: 1.24E5 Ci/g [4,600 TBq/g] max. II. RADIOLOGICAL DATA Radiotoxicity2: 4.76 E-7 Sv/Bq (1.76 rem/uCi) of 131I ingested [Thyroid] 2.92 E-7 Sv/Bq (1.08 rem/uCi) of 131I inhaled [Thyroid] Critical Organ: Thyroid Gland Intake Routes: Ingestion, inhalation, puncture, wound, skin contamination (absorption); Radiological Hazard: External & Internal Exposure; Contamination III. SHIELDING Half Value Layer [HVL] Tenth Value Layer [TVL] Lead [Pb]3 3 mm (0.12 inches) 11 mm (0.43 inches) - The accessible dose rate should be background but must be < 2 mR/hr IV. DOSIMETRY MONITORING - Always wear radiation dosimetry monitoring badges [body & ring] whenever handling 131I - Conduct a baseline thyroid scan prior to first use of radioactive iodine - Conduct thyroid bioassay measurement [at neck just above collar bone] no earlier than 6 hours but within 72 hours of handling 1 mCi or more of 131I or after any suspected intake V. DETECTION & MEASUREMENT Portable Survey Meters: Geiger-Mueller [e.g. PGM] to assess shielding effectiveness & contamination Wipe Test: Liquid Scintillation Counter or Gamma Counter VI.
    [Show full text]
  • Leukoscan, INN-Sulesomab
    authorised ANNEX I longer SUMMARY OF PRODUCT CHARACTERISTICS no product Medicinal 1 1. NAME OF THE MEDICINAL PRODUCT LeukoScan 0.31 mg, powder for solution for injection 2. QUALITATIVE AND QUANTITATIVE COMPOSITION Kit for the preparation of 99mTc-labelled LeukoScan. Each 3 ml vial contains 0.31 mg sulesomab (IMMU-MN3 murine Fab′-SH antigranulocyte monoclonal antibody fragments) for the preparation of 99mTc labelled LeukoScan. The kit does not include the radioisotope. Excipients: Sucrose (37.8 mg) For a full list of excipients, see section 6.1. authorised 3. PHARMACEUTICAL FORM Powder for solution for injection. 4. CLINICAL PARTICULARS longer 4.1 Therapeutic indications This medicinal product is for diagnostic use only. no LeukoScan is indicated for diagnostic imaging for determining the location and extent of infection/inflammation in bone in patients with suspected osteomyelitis, including patients with diabetic foot ulcers. LeukoScan has not been employed to diagnose osteomyelitis in patients with sickle cell anaemia. 4.2 Posology and methodproduct of administration The radiolabelled solution should be administered as an intravenous injection. After injection, any remaining portion of the reconstituted solution should be discarded. LeukoScan is not recommended for use in children. Formal studies have not been performed in patients with renal or hepatic impairment. However, due to the low dose of protein administered and the short half-life of 99mTc, dosage adjustment is probably not necessary in such patients. Medicinal Radiopharmaceutical agents should be used only by qualified personnel with appropriate government authorisation for the use and manipulation of radionuclides. 2 This radiopharmaceutical may be received, used and administered only by authorised persons in designated clinical settings.
    [Show full text]
  • Ionizing Radiation in Earth's Atmosphere and in Space Near Earth May 2011 6
    Federal Aviation Administration DOT/FAA/AM-11/9 Office of Aerospace Medicine Washington, DC 20591 Ionizing Radiation in Earth’s Atmosphere and in Space Near Earth Wallace Friedberg Kyle Copeland Civil Aerospace Medical Institute Federal Aviation Administration Oklahoma City, OK 73125 May 2011 Final Report OK-11-0024-JAH NOTICE This document is disseminated under the sponsorship of the U.S. Department of Transportation in the interest of information exchange. The United States Government assumes no liability for the contents thereof. ___________ This publication and all Office of Aerospace Medicine technical reports are available in full-text from the Civil Aerospace Medical Institute’s publications Web site: www.faa.gov/library/reports/medical/oamtechreports Technical Report Documentation Page 1. Report No. 2. Government Accession No. 3. Recipient's Catalog No. DOT/FAA/AM-11/9 4. Title and Subtitle 5. Report Date Ionizing Radiation in Earth's Atmosphere and in Space Near Earth May 2011 6. Performing Organization Code 7. Author(s) 8. Performing Organization Report No. Friedberg W, Copeland K 9. Performing Organization Name and Address 10. Work Unit No. (TRAIS) FAA Civil Aerospace Medical Institute P.O. Box 25082 11. Contract or Grant No. Oklahoma City, OK 73125 12. Sponsoring Agency name and Address 13. Type of Report and Period Covered Office of Aerospace Medicine Federal Aviation Administration 800 Independence Ave., S.W. Washington, DC 20591 14. Sponsoring Agency Code 15. Supplemental Notes 16. Abstract The Civil Aerospace Medical Institute of the FAA is charged with identifying health hazards in air travel and in commercial human space travel.
    [Show full text]
  • I Nuclide Safety Data Sheet Iodine-123
    123 Nuclide Safety Data Sheet 123 Iodine-123 I www.nchps.org I I. PHYSICAL DATA Radiation: Electrons – 3 keV (94%); 23 keV (12%); 127 keV (14%); others (<2%) Gamma & X-ray – 159 keV (83%); 27 keV (70%); 31 keV (16%); others (< 10%) a Gamma Constant: 0.277 mrem/hr per mCi @ 1.0 meter [7.478 E-5 mSv/hr per MBq @ 1.0 meter] a Half-Life [T½] : Physical T½: 13.13 hours Biological T½: 120-138 days (unbound iodine) Effective T½: ~ 12 hours (unbound iodine) Specific Activity: 1.93E6 Ci/g [7.14E16 Bq/g] max.b II. RADIOLOGICAL DATA Radiotoxicityc: 4.42 E-9 Sv/Bq (16 mrem/uCi) of 123I ingested [Thyroid] 2.25 E-9 Sv/Bq (8.3 mrem/uCi) of 123I inhaled [Thyroid] Critical Organ: Thyroid Gland Intake Routes: Ingestion, inhalation, puncture, wound, skin contamination (absorption); Radiological Hazard: External & Internal Exposure; Contamination III. SHIELDING Half Value Layer [HVL] Tenth Value Layer [TVL] Lead [Pb]b 1 mm (0.04 inches) 2 mm (0.08 inches) - The accessible dose rate should be background but must be < 2 mR/hr IV. DOSIMETRY MONITORING - Always wear radiation dosimetry monitoring badges [body & ring] whenever handling 123I - Conduct a baseline thyroid scan prior to first use of radioactive iodine - Conduct thyroid bioassay measurement [at neck just above collar bone] no earlier than 6 hours but within 72 hours of handling 1 mCi (37 MBq) or more of 123I or after any suspected intake V. DETECTION & MEASUREMENT Portable Survey Meters: Geiger-Mueller [e.g. Bicron PGM] to assess shielding effectiveness Low Energy Gamma Detector [e.g.
    [Show full text]