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Manual for Reactor Produced Radioisotopes

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Manual for Reactor Produced Radioisotopes IAEA-TECDOC-1340 Manual for reactor produced radioisotopes January 2003 The originating Section of this publication in the IAEA was: Industrial Applications and Chemistry Section International Atomic Energy Agency Wagramer Strasse 5 P.O. Box 100 A-1400 Vienna, Austria MANUAL FOR REACTOR PRODUCED RADIOISOTOPES IAEA, VIENNA, 2003 IAEA-TECDOC-1340 ISBN 92–0–101103–2 ISSN 1011–4289 © IAEA, 2003 Printed by the IAEA in Austria January 2003 FOREWORD Radioisotopes find extensive applications in several fields including medicine, industry, agriculture and research. Radioisotope production to service different sectors of economic significance constitutes an important ongoing activity of many national nuclear programmes. Radioisotopes, formed by nuclear reactions on targets in a reactor or cyclotron, require further processing in almost all cases to obtain them in a form suitable for use. Specifications for final products and testing procedures for ensuring quality are also an essential part of a radioisotope production programme. The International Atomic Energy Agency (IAEA) has compiled and published such information before for the benefit of laboratories of Member States. The first compilation, entitled Manual of Radioisotope Production, was published in 1966 (Technical Reports Series No. 63). A more elaborate and comprehensive compilation, entitled Radioisotope Production and Quality Control, was published in 1971 (Technical Reports Series No. 128). Both served as useful reference sources for scientists working in radioisotope production worldwide. The 1971 publication has been out of print for quite some time. The IAEA convened a consultants meeting to consider the need for compiling an updated manual. The consultants recommended the publication of an updated manual taking the following into consideration: – significant changes have taken place since 1971 in many aspects of radioisotope production; – many radioisotopes have been newly introduced while many others have become gradually obsolete; – considerable experience and knowledge have been gained in production of important radioisotopes over the years, which can be preserved through compilation of the manual; – there is still a need for a comprehensive manual on radioisotope production methods for new entrants to the field, and as a reference. It was also felt that updating all the subjects covered in the 1971 manual at a time may not be practical considering the numerous new developments that have taken place since then. Hence in this manual it was decided to focus only on reactor produced radioisotopes. This manual contains procedures for 48 important reactor-produced isotopes. These were contributed by major radioisotope producers from different parts of the world and are based on their practical experience. In case of widely used radioisotopes such as 131I, 32P and 99Mo, information from more than one centre is included so that the users can compare the procedures. As in the earlier two versions, a general introductory write-up is included covering basic information on related aspects such as target irradiation, handling facilities, radiation protection and transportation, but in less detail. Relevant IAEA publications on such matters, particularly related to radiation protection and transportation, should be referred to for guidelines. Similarly, the nuclear data contained in the manual are only indicative and the relevant databases should be referred to for more authentic values. It is hoped that the manual will be a useful source of information for those working in radioisotope production laboratories as well as those intending to initiate such activities. The IAEA wishes to thank the consultants and all the contributors for their co-operation in compiling the manual. The IAEA officers responsible for this publication were D.V.S. Narasimhan and H. Vera Ruiz of the Division of Physical and Chemical Sciences. EDITORIAL NOTE This publication has been prepared from the original material as submitted by the authors. The views expressed do not necessarily reflect those of the IAEA, the governments of the nominating Member States or the nominating organizations. The use of particular designations of countries or territories does not imply any judgement by the publisher, the IAEA, as to the legal status of such countries or territories, of their authorities and institutions or of the delimitation of their boundaries. The mention of names of specific companies or products (whether or not indicated as registered) does not imply any intention to infringe proprietary rights, nor should it be construed as an endorsement or recommendation on the part of the IAEA. The authors are responsible for having obtained the necessary permission for the IAEA to reproduce, translate or use material from sources already protected by copyrights. CONTENTS 1. PRINCIPLES OF PRODUCTION, PROCESSING AND HANDLING OF RADIOISOTOPES ........................................................................................................ 1 1.1. Introduction ................................................................................................................ 1 1.2. Research reactors for isotope production ................................................................... 2 1.3. Nuclear reactions........................................................................................................2 1.3.1. Energy of neutrons in pile.............................................................................. 4 1.3.2. Cross-section.................................................................................................. 4 1.3.3. Types of nuclear reactions ............................................................................. 4 1.4. Calculation of radioisotope yield ............................................................................... 6 1.4.1. Corrections to the activation equation ........................................................... 7 1.4.2. Self-shielding effect ...................................................................................... 7 1.4.3. Power variation in the reactors....................................................................... 8 1.4.4. Corrections for burnup of the target and destruction of target atoms ............ 8 1.4.5. Irradiation efficiency...................................................................................... 9 1.5. Irradiation techniques............................................................................................... 10 1.5.1. Choice of target material ................................................................................ 10 1.5.2. Target encapsulation ...................................................................................... 11 1.5.3. Safety evaluation of in-pile irradiation and experimental assemblies............ 11 1.6. Laboratory facilities for radioisotope production..................................................... 11 1.6.1. Layout and basic infrastructure.................................................................... 12 1.6.2. Radiological protection................................................................................ 13 1.6.3. Radioisotope handling facilities................................................................... 13 1.6.4. Ventilation.................................................................................................... 16 1.6.5. Management of radioactive waste................................................................ 16 1.6.6. Surveillance and monitoring........................................................................ 17 1.7. Packing and transportation of radioisotopes ........................................................... 18 1.7.1. Transport regulations ................................................................................... 18 1.7.2. Types of packages........................................................................................ 18 1.7.3. Categories of packages................................................................................. 20 1.8. Conclusion................................................................................................................ 20 Bibliography to Section 1......................................................................................................... 21 2. PRODUCTION AND PROCESSING METHODS FOR INDIVIDUAL RADIOISOTOPES 82 Bromine-82 ( Br35).................................................................................................................. 25 45 Calcium-45 ( Ca20) ................................................................................................................. 29 14 Carbon-14 ( C6) ...................................................................................................................... 31 51 Chromium-51 ( Cr24) .............................................................................................................. 35 58 Cobalt-58 ( Co27) .................................................................................................................... 41 60 Cobalt-60 ( Co27) .................................................................................................................... 44 64 67 Copper-64/Copper-67 ( Cu29, Cu29)..................................................................................... 51 165 Dysprosium-165 ( Dy66)........................................................................................................ 58 166 Dysprosium-166 ( Dy66).....................................................................................................
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