Production of Long Lived Parent Radionuclides - IAEA Publications

128 Pages·2010·2.62 MB·English

IAEA RADIOISOTOPES AND RADIOPHARMACEUTICALS SERIES No. 2
This book provides information on the production and processing
of four important long lived parent radionuclides, 68Ge, 82Sr,
90Sr and 188W, used for the preparation of generators for nuclear
medicine applications such as positron emission tomography
and therapy. It includes descriptions of the production routes
for and process chemistry of the selected parent radionuclides,
including relevant separation approaches. Information on use of
the generator system and on physical and chemical characteristics
is also provided.
Production of Long Lived
Parent Radionuclides
for Generators:
68 82 90 188
Ge, Sr, Sr and W
INTERNATIONAL ATOMIC ENERGY AGENCY
VIENNA
ISBN 978–92–0–101110–7
ISSN 2077–6462
10-03151_P1436_cover.indd 1 2010-05-06 10:29:07
Production of Long Lived Parent Radionuclides for Generators: 68Ge, 82Sr, 90Sr and 188W
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sources development/production for medical and industrial uses; radiopharmaceutical sciences, THERAPEUTIC RADIONUCLIDE GENERATORS:
including radiochemistry, radiotracer development, production methods and quality assurance/ 90 90 188 188
SR/ Y AND W/ RE GENERATORS
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There are two categories of publications: the IAEA Radioisotopes and CYCLOTRON PRODUCED RADIONUCLIDES:
Radiopharmaceuticals Series and IAEA Radioisotopes and Radiopharmaceuticals Reports. PHYSICAL CHARACTERISTICS AND PRODUCTION METHODS
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TECHNETIUM RADIOPHARMACEUTICALS:
IAEA RADIOISOTOPES AND RADIOPHARMACEUTICALS REPORTS MANUFACTURE OF KITS
In this category, publications complement information published in the IAEA Radioisotopes Technical Reports Series No. 466
and Radiopharmaceuticals Series in areas of the: development and production of radioisotopes and
STI/DOC/010/466 (202 pp.; 2008)
generators for medical and industrial applications; and development, production and QA/QC of
ISBN 978–92–0–100408–6 Price: €50.00
diagnostic and therapeutic radiopharmaceuticals. These publications include reports on current
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PRINCIPLES AND PRACTICE
dealing with radioisotope and radiopharmaceutical related subjects. In some cases, these reports
may provide supporting material relating to publications issued in the IAEA Radioisotopes and Technical Reports Series No. 465
Radiopharmaceuticals Series. STI/DOC/010/465 (230 pp.; 2008)
ISBN 978–92–0–100208–2 Price: €45.00
All of these publications can be downloaded cost free from the IAEA web site:
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http://www.iaea.org/Publications/index.html RADIOPHARMACEUTICALS
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TRENDS IN RADIOPHARMACEUTICALS (2 volumes)
PRODUCTION OF LONG LIVED
PARENT RADIONUCLIDES FOR
68 82 90 188
GENERATORS: Ge, Sr, Sr AND W
The following States are Members of the International Atomic Energy Agency:
AFGHANISTAN GHANA NORWAY
ALBANIA GREECE OMAN
ALGERIA GUATEMALA PAKISTAN
ANGOLA HAITI PALAU
ARGENTINA HOLY SEE
PANAMA
ARMENIA HONDURAS
PARAGUAY
AUSTRALIA HUNGARY
PERU
AUSTRIA ICELAND
PHILIPPINES
AZERBAIJAN INDIA
POLAND
BAHRAIN INDONESIA
PORTUGAL
BANGLADESH IRAN, ISLAMIC REPUBLIC OF
QATAR
BELARUS IRAQ
REPUBLIC OF MOLDOVA
BELGIUM IRELAND
ROMANIA
BELIZE ISRAEL
RUSSIAN FEDERATION
BENIN ITALY
SAUDI ARABIA
BOLIVIA JAMAICA
SENEGAL
BOSNIA AND HERZEGOVINA JAPAN
SERBIA
BOTSWANA JORDAN
SEYCHELLES
BRAZIL KAZAKHSTAN
SIERRA LEONE
BULGARIA KENYA
BURKINA FASO KOREA, REPUBLIC OF SINGAPORE
BURUNDI KUWAIT SLOVAKIA
CAMBODIA KYRGYZSTAN SLOVENIA
CAMEROON LATVIA SOUTH AFRICA
CANADA LEBANON SPAIN
CENTRAL AFRICAN  LESOTHO SRI LANKA
REPUBLIC LIBERIA SUDAN
CHAD LIBYAN ARAB JAMAHIRIYA SWEDEN
CHILE LIECHTENSTEIN
SWITZERLAND
CHINA LITHUANIA
SYRIAN ARAB REPUBLIC
COLOMBIA LUXEMBOURG
TAJIKISTAN
CONGO MADAGASCAR
THAILAND
COSTA RICA MALAWI
THE FORMER YUGOSLAV 
CÔTE D’IVOIRE MALAYSIA
REPUBLIC OF MACEDONIA
CROATIA MALI
TUNISIA
CUBA MALTA
TURKEY
CYPRUS MARSHALL ISLANDS
UGANDA
CZECH REPUBLIC MAURITANIA
UKRAINE
DEMOCRATIC REPUBLIC  MAURITIUS
UNITED ARAB EMIRATES
OF THE CONGO MEXICO
UNITED KINGDOM OF 
DENMARK MONACO
GREAT BRITAIN AND 
DOMINICAN REPUBLIC MONGOLIA
NORTHERN IRELAND
ECUADOR MONTENEGRO
UNITED REPUBLIC 
EGYPT MOROCCO
OF TANZANIA
EL SALVADOR MOZAMBIQUE
UNITED STATES OF AMERICA
ERITREA MYANMAR
URUGUAY
ESTONIA NAMIBIA
UZBEKISTAN
ETHIOPIA NEPAL
FINLAND NETHERLANDS VENEZUELA
FRANCE NEW ZEALAND VIETNAM
GABON NICARAGUA YEMEN
GEORGIA NIGER ZAMBIA
GERMANY NIGERIA ZIMBABWE
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contribution of atomic energy to peace, health and prosperity throughout the world’’.
IAEA RADIOISOTOPES AND RADIOPHARMACEUTICALS SERIES No. 2
PRODUCTION OF LONG LIVED
PARENT RADIONUCLIDES FOR
68 82 90 188
GENERATORS: Ge, Sr, Sr AND W
INTERNATIONAL ATOMIC ENERGY AGENCY
VIENNA, 2010
COPYRIGHT NOTICE
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FOREWORD
Radionuclide generators represent convenient in-house radionuclide
production systems that allow daughter species to be obtained even in the absence
of on-site reactor or accelerator facilities. The resurgence in interest in the use of
radionuclide generator systems is due to the development of new targeting
strategies using specific carrier molecules for the development of both diagnostic
and therapeutic radiopharmaceuticals.
This publication provides information on the production and processing of
68 82 90 188
four important long lived parent radionuclides, Ge, Sr, Sr and W, used for
the preparation of generators for nuclear medicine applications such as positron
68 68
emission tomography (PET) or therapy. Germanium-68 is used for the Ge/ Ga
68
generator system, which provides no-carrier-added Ga for use in PET imaging.
Gallium-68 labelled tumour specific peptides are now in routine use for PET
imaging of certain types of cancer. Strontium-82 is used as the parent for the
82 82
production of Sr/ Rb generator systems. Rubidium-82 is an important PET
marker for myocardial perfusion studies. This report describes the processing and
90 90
purification of Sr from fission products, which can provide Sr suitable for
90 90
fabrication of the Sr/ Y generator. Yttrium-90 is widely used for a variety of
important therapeutic applications. Reactor production and subsequent
188
processing of W provides this important parent species for fabrication of the
188 188 188
W/ Re generator system to obtain Re perrhenate for incorporation into
various therapeutic agents.
The IAEA thanks all the consultants who contributed to this publication, as
well as the reviewers. F.F. Knapp, Jr., of the Oak Ridge National Laboratory,
USA, provided valuable help in editing the manuscript. The IAEA officer
responsible for this publication was M.R.A. Pillai of the Division of Physical and
Chemical Sciences.
EDITORIAL NOTE
The use of particular designations of countries or territories does not imply any
judgments 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
CHAPTER 1. INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
1.1. Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
1.2. Objective . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7
1.3. Scope . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
1.4. Structure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
References to Chapter 1 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
CHAPTER 2. PRODUCTION, RADIOCHEMICAL PROCESSING
68
AND QUALITY EVALUATION OF Ge . . . . . . . . . . . . 11
F. Roesch, D.V. Filosofov
2.1. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11
2.2. Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12
2.3. Nuclear decay characteristics . . . . . . . . . . . . . . . . . . . . . . . . . . . 15
68
2.4. Ge production . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15
2.5. Chemical aspects . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24
2.6. Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27
References to Chapter 2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28
82
CHAPTER 3. PRODUCTION AND PROCESSING OF Sr . . . . . . . . . 31
K.D. John, L. Mausner, T.J. Ruth
3.1. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31
3.2. Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32
3.3. Nuclear decay characteristics . . . . . . . . . . . . . . . . . . . . . . . . . . . 32
3.4. Production processes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 33
3.5. Chemical aspects . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 39
3.6. Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42
References to Chapter 3 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 42
Bibliography . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 44
CHAPTER 4. RECOVERY, PURIFICATION AND QUALITY
90
EVALUATION OF Sr . . . . . . . . . . . . . . . . . . . . . . . . . . . 49
S.K. Samanta
4.1. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 49
4.2. Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50
4.3. Nuclear decay characteristics . . . . . . . . . . . . . . . . . . . . . . . . . . . 54
90
4.4. Processes for the recovery of Sr from radioactive waste . . . . 55
4.5. Purification . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 69
90
4.6. Methods for evaluation of the quality of Sr . . . . . . . . . . . . . . . 71
4.7. Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 73
Acknowledgements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 75
References to Chapter 4 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 75
CHAPTER 5. REACTOR PRODUCTION 
188
AND PROCESSING OF W . . . . . . . . . . . . . . . . . . . . . . 79
F.F. Knapp, Jr., S. Mirzadeh, M. Garland, B. Ponsard,
R. Kuznetsov
5.1. Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 79
5.2. Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 80
5.3. Nuclear decay . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 81
5.4. Production and processing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 81
5.5. Chemical aspects . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 87
188
5.6. Processing of W . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 89
5.7. Radiological controls and radiation protection . . . . . . . . . . . . . 98
5.8. Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 105
Acknowledgements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 106
References to Chapter 5 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 106
CONTRIBUTORS TO DRAFTING AND REVIEW . . . . . . . . . . . . . . . . . 111