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`JUBILANT EXHIBIT 1030
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`JUBILANT EXHIBIT 1030
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`CRITICAL REVIEWS™
`QUARTERLY JOURNALS
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`CRITICAL REVIEWS in ANALYTICAL CHEMISTRY
`Edited by Louis Meites, Ph.D., Chairman, Department of Chemistry, Clarkson College
`of Technology. Associate Editor:Gunter Zweig, Ph.D. , Director, Life Sciences Division,
`Syracuse University Research Corp. Assistant Editor: Irving Sunshine, Ph.D., Chief
`Toxicologist, Cuyahoga County Coroner's Office, Ohio .
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`CRITICAL REVIEWS in CLINICAL LABORATORY SCIENCES
`Edited by John W. King, M.D. , Ph.D., Director of Clinical Laboratories, Cleveland
`Clinic Foundation, and Willard R. Faulkner, Ph.D., Vanderbilt University Medical
`Center.
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`CRITICAL REVIEWS in ENVIRONMENTAL CONTROL
`Edited by Richard G. Bond, M.P.S., Director of Environmental Health, University of
`Minnesota, and Conrad P. Straub, Director, Environmental Health Research and
`Training Center, University of Minnesota.
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`OcRmCAL REVIEWS in FOOD TECHNOLOGY
`Edited by Thomas E. Furia, Technical Development Manager, Industrial Chemicals
`Division, Geigy Chemical Corporation .
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`CRITICAL REVIEWS in RADIOLOGICAL SCIENCES
`Edited by Yen Wang, M.D., D.Sc. , Chairman, Department of Radiology, Homestead
`Hospital, Pittsburgh .
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`CRITICAL REVIEWS in SOLID STATE SCIENCES
`Edited by Donald E. Schuele, Ph.D., and Richard Hoffman, Ph.D., both of the
`Department of Physics, Case Western Reserve University.
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`THE CHEMICAL RUBBER CO. 0 HANDBOOK SERIES
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`Vice-President, Research, Consolidated Natural Gas Service Company, Inc.
`Formerly Professor of Chemistry at Case Institute of Technology
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`Coordinating Editor
`GEORGE L. TUVE, Sc.D.
`Formerly Professor of Engineering at Case Institute of Technology
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`Editor-in-Chief of Mathematics
`SAMUEL M. SELBY, Ph.D.
`Di!>tinguished Professor Emeritus
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`University of Akron
`Presently Chairman of Mathematics Department
`Hiram College
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`Editor-in-Chief of Biosciences
`IRVING SUNSHINE, Ph.D.
`Chief Toxicologist
`Cuyahoga County Coroner's Office
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`Associate Professor of Toxicology
`Case Western Reserve University
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`Editors
`Chromatography
`Gunter Zweig, Ph.D.
`Engineering Sciences
`Ray E. Bolz, D.Eng.
`Richard G. Bond, M.P.H.
`Donald F. Gibbons, Ph.D.
`W. Bruce Johnson, Ph.D.
`Conrad P. Straub, Ph.D., D.Eng.
`Laboratory Safety
`Norman V. Steere
`Life Sciences
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`John W. King, M.D., Ph.D .
`eaJ S. Nelson, Ph.D.
`Herbert A. Sober, Ph.D.
`Mathematics
`Brian Girling, M.Sc., F.I.M.A.
`Nuclear Sciences
`Yen Wang, M.D., D.Sc.(Med.)
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`Zvi Rappoport, Ph.D.
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`The Cleveland Clinic Foundation
`Radionuclide Toxicology Laboratory
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`Hebrew University of Jerusalem
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`University of Akron
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`6 of 59
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`

`Handbook
`of
`Radioactive Nuclides
`
`EDITOR
`Yen Wang, M.D., D.Sc.(Med.)
`Director, Department of Radiology
`Homestead Hospital
`Homestead, Pennsylvania
`
`Published by
`THE CHEMICAL RUBBER CO.
`18901 Cranwood Parkway, Cleveland, Ohio 44128
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`This book presents data obtained from authentic and highly
`regarded sources. Reprinted material is quoted with permission,
`and sources are indicated. A wide variety of references are listed.
`Every reasonable effort has been made to give reliable data and
`information, but the editor and the publisher cannot assume
`responsibility for the validity of the material or for the consequences
`of its application.
`
`© 1969 by The Chemical Rubber Co.
`All Rights Reserved
`Library of Congress Card No. 75-81089
`
`8 of 59
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`

`

`PREFACE
`
`In the preparation of this reference volume, the aim has been to provide a convenient
`single source for basic information on radioactive nuclides, instrumentation, dosimetry, and
`applications, as well as on genera:\ radiation protection. Most of the information is in tabular
`or graphical form, but narrative presentation and explanation are also included. For con(cid:173)
`venient reference, the Handbook has been divided into several sections, many of which cover
`special applications of radionuclides.
`A considerable proportion of the material herein has been compiled especially for this
`book from current scientific journals and from various authoritative collections of basic
`radionuclide data and applications. The editors are grateful for permissions to reprint these
`materials and have made every effort to designate the original sources and to give references
`to further information available on each subject.
`Although the editors have tried to include in condensed form the information most
`frequently used and needed in the fields of radionuclide application, there is always a question
`of what to include in a one-volume desk-reference book. Suggestions from readers for additions
`or modifications in future editions are invited.
`We would like to take this opportunity to express our deep gratitude to our contributors
`and to the members of the editorial board as well as to others who have assisted us in the
`compilation of this volume. The information on radionuclides is so voluminous that the
`completion of the book would not have been possible without their effort and assistance.
`
`YEN WANG
`
`June 1969
`
`413233
`
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`

`TABLE OF CONTENTS
`
`PART I. NUCLEAR DATA
`3
`Jsotopes. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
`7
`Radioisotope Production and Processing. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
`Physical and Nuclear Data.......................... .. ....... . ....... . . ... . . . . .. 16
`
`PART II. ESSENTIAL PHYSICS DATA
`
`Radiation Interaction with Matter . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 67
`Statistical Aspects of Nuclear Counting. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 77
`
`PART III. NUCLEAR INSTRUMENTATION
`
`Radiation Detectors and Equipment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 89
`Radioisotope Counting and Calibration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 106
`Improvement of Liquid Scintillation Counting Efficiencies by Optimization of Scintillator
`Composition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 114
`Modulation Transfer Function for Radioisotope Imaging Systems. . . . . . . . . . . . . . . . . . . . 123
`Personnel Monitoring . . . .................... . .. .. ..................... . . ...... . 130
`Whole-Body Counter Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 134
`Information Storage and Retrieval in Radioisotope Imaging Systems . . . . . . . . . . . . . . . . . 141
`Radioisotope Cameras ......... . ......... ................. ... . .. . ...... . ....... 148
`
`PART IV. RADIATION DOSIMETRY
`
`Radiation Absorbed-Dose Calculations for Biologically Distributed Radionuclides ...... 167
`Radiation Doses from Administered Radionuclides .......... ... ........ . .......... 201
`Dose from Ingestion or Inhalation of Soluble Radionuclides . . . . . . . . . . . . . . . . . . . . . . . . 220
`
`PART V. BIOCHEMISTRY
`
`Standards of Activity. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 229
`. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 237
`Radioactive Isotope Dilution Analysis
`Improved Solubilization Procedures for Liquid Scintillation Counting of Biological
`Materials ... .... .. . .............. . .. . ...... . ..... . . . . ... ............. ... . . 246
`Sample Preparation for Liquid Scintillation Counting . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 256
`The Stability of Labeled Organic Compounds . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 274
`Storage and Stability of Compounds Labeled with Radioisotopes. I . . . . . . . . . . . . . . . . . . 285
`Storage and Stability of Compounds Labeled with Radioisotopes. II . . . . . . . . . . . . . . . . . 315
`Synthesis of Labeled Compounds. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 339
`
`PART VI. RADIONUCLIDES FOR MEDICAL APPLICATION
`
`Cerebronervous Applications. I. Measurement of Cerebral Blood Flow . . . . . . . . . . . . . . . 383
`Cerebronervous Applications. II. Brain Scanning ...... . ........ . ... . ...... . ....... 388
`Radionuclides and the Endocrine System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 395
`Radionuclide Diagnosis of Cardiovascular Disease . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 423
`
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`xii
`
`Handbook of Radioactive Nuclides
`
`Radionuclides in Respiratory-System Studies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 434
`Nuclear-Medicine Techniques in Gastroenterologic Diagnosis ..... . .... ............. 443
`The Use of Radioisotopes in the Osseous and Cartilaginous System . . . . . . . . . . . . . . . . . . 466
`Radioisotopes and the Hematopoietic System .. . ....... .. . . ............ . ... . ...... 477
`Radionuclide Techniques Applied to the Genitourinary System . . . . . . . . . . . . . . . . . . . . . . 492
`
`PART VII. RADIONUCLIDES FOR INDUSTRIAL APPLICATIONS
`Characteristic Effects of Radiation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 503
`Availability of Isotopes .. . ..................... . .................. . ............. 505
`Radioisotope Utilization. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 507
`Applications in the Metals Industries . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 509
`Applications in the Electrical Industry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 515
`Applications in Transportation-Equipment Industries ............. .... .............. 517
`Applications in Chemical Processing ... ................. . ........ . ....... ........ 5 I 9
`Applications in Consumer-Products Industries ........... ............ .. ............ 531
`Applications in Crude-Petroleum and Natural-Gas Industries. . . . . . . . . . . . . . . . . . . . . . . . 540
`Applications in Mining. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 544
`Applications in the Utilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 547
`Applications in Agriculture . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 550
`Applications in Aerospace and Other Environmental Uses . . . . . . . . . . . . . . . . . . . . . . . . . . 557
`Glossary. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 569
`
`PART VIII. RADIATION PROTECTION AND REGULATIONS
`Basic Units of Radiation Measurement ..................................... ..... 573
`Radiation Protection Guides and Regulatory Limits of Exposure . . . . . . . . . . . . . . . . . . . . 609
`Data and Methods for Estimating Radiation Exposures from Internal and External
`Radiation Sources . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 647
`Determination of Facilities, Equipment, a nd Procedures Required for Various Types of
`Operations. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 664
`Personnel Dosimetry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 711
`Transportation of Radioactive Materials
`. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 719
`Radioactive-Waste Disposal ......................................... .. ........ .. 781
`Administration of a Radiation-Protection Program.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 795
`Emergency Planning and Procedures ..... . ....... ..... . .. . ..................... .. 799
`Appendix 1. Emergency Notification Instructions ........................ . .... .... 816
`Appendix 2. Radiation-fncident Evaluation Record ............. . .. . .. . ... ... . .... 818
`Appendix 3. Radiation-Incident Evaluation Record .. . ........................ . ... 819
`Appendix 4. U.S. Atomic Energy Commission Regional Office Areas of Responsibility
`for Radiological Assistance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 820
`Appendix 5. Evaluation of Personnel-Monitoring Results .......... ... ............. 822
`Appendix 6. A Suggested Check List on Radiation-Accident Preparedness . . . . . . . . . . . 823
`Appendix 7. Evaluation of Incidents or Occurrences Involving Radiation ............ 826
`Appendix 8. Radiation-Incident Reporting Procedures ................... ......... 828
`Appendix 9. U.S. Atomic Energy Commission Regional Compliance Offices ......... 830
`Appendix 10. Records, Reports, and Notifications pertinent to Radiation Incidents ... 831
`
`PART IX. RADIATION INJURY AND ITS MANAGEMENT
`Standard Man ...... . ............ .. ............................ . ..... . .... .. ... 837
`Radiation I njury .. ....... .... . ....... .. ..... . ..... .. ........................... 845
`Medical Management of Radiation Emergencies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 868
`
`11 of 59
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`

`

`Table of Contents
`
`PART X. REFERENCE DATA
`
`xiii
`
`Greek Alphabet . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 887
`Signs and Symbols of Particular Interest in Radiation and Rad ioactivity . ... ..... ... .. 888
`Signs and Symbols in Mathematics. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 890
`Abbreviations ... ............ ... ..................... . ......................... 891
`Commonly Used Units ........................................................ . 894
`Fundamental Constants . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 895
`The Standard Man (Conventional) ............................................... 897
`Densities of Common Metals .... . .. ... . . . ....................................... 899
`Relation Between Thicknesses of Ordinary Concrete and of Lead for Radium and 6°Co
`Gamma Rays . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 900
`Nomogram of Absorption of Beta Particles ........ . . .. . ....... .. ..... .. ..... .... . 901
`Decay Curve for Radioactive Materials . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 902
`Radioactive Decay. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 903
`Referential Conversion Factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 904
`Convenient Conversion Factors ........ . .. .... .. ...... . .............. .. .. . .. . . ... 905
`Equations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 909
`Four-Place Mantissas for Common Logarithms of Decimal Fractions ... .... . . ....... 919
`Four-Place Mantissas for Common Logarithms .................................... 921
`Natural Trigonometric Functions, Sine, Cosine, Tangent, Cotangent, for Angles, in
`Degrees and in Decimals .................. . . .. . . ........ . . .. .. . ... ... ...... . 923
`Exponential Functions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 928
`Squares, Square Roots, Cubes, and Cube Roots ... .... .. . . .................. .... .. 932
`
`INDEX
`
`943
`
`12 of 59
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`

`DETERMINATION OF FACILITIES,
`EQUIPMENT, AND PROCEDURES
`REQUIRED FOR VARIOUS TYPES
`OF OPERATIONS
`Allen Brodsky, Sc.D., C.H.P.
`
`There are already many good references on general safety procedures and proper design
`considerations for laboratories or facilities using radioactive material or radiation sources.1
`5
`-
`This chapter will summarize only some of the general considerations in selecting appropriate
`facilities, equipment and procedures, including Table 41 , which arranges the radionuclides
`according to intrinsic radiotoxicity along with the respective radioactivity levels above which
`various safeguards or combinations of several safeguards should be considered. 6
`A check list of considerations involved in determining the types of facilities, equipment,
`and procedures that might be required for handling radioactive materials in quantities large
`enough to be of some potential hazard to personnel is given below, presented in a format
`such as one might find in a hazard summary report prepared for a licensing review.
`
`INFORMATION TO BE INCLUDED
`IN A HAZARD SUMMARY REPORT*
`I. A Description of Operations or Applications
`Involving Radioactive Materials.
`Include (as applicable to operations with radioactive material) a description
`of any chemical, physical, metallurgical, or nuclear processes to be carried
`out. The description should be detailed enough to permit evaluation of
`the radiation hazards involved. The forms and amounts of radioactivity
`to be handled in the proposed processes and any thermal energy likely to
`be generated should be given.
`II. A Description of Facilities and Equipment.
`Describe the ~esign criteria for the facility as a whole and for those parts
`that a~e essential to the safe operation of the facility. The description should
`contam enough detail to allow an evaluation of the various methods
`propo~ed to minimize any chances of exposing persons on or off site to
`excessive amounts of radiation or radioactive materials. The description
`shoul~ also cov~r any activities (in addition to those involving radioactive
`material) that will be carried on in the building that will house the facility
`and on ~he ba~a~ce of the site. The description should include, but not
`necessarily be limited to such items as· shield.
`t be
`·d d ·
`I d. g
`'
`·
`mg o
`prov1 e , me u m
`.
`t
`f
`1
`ypes o ma eria
`dens1·ti·es d.
`·
`.
`t
`.
`.
`.
`,
`,
`tmens1ons, and attenuations expected;
`detailed descriptions of rad· ti
`·
`·
`·
`. . . .
`ta on momtormg systems and alarms and their
`sensitlVltles; fea~ure~ of the air ventilation and filtration systems that will
`prevent contammation of u
`t · d
`nres ricte areas or nearby farms and com-
`
`f
`I t" 1
`• The items indicated are intended to serve as a
`.
`0
`these items may not be applicable or may require only b,~:r: ive Y exhaushve chcck_Hst; however, for individual installations man'.
`nswers. In some cases, ttems not indicated in this list may deserve menuon.
`
`664
`
`13 of 59
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`

`Radiation Protection and Regulations
`
`665
`
`Table 41.
`RADIOTOXICITY VERSUS LEVELS
`ABOVE WIIlCH VARIOUS SAFEGUARDS MA y BE REQUIRED6
`(See footnotes at end of table.)
`
`Radionuclides
`
`Physical Properties
`
`Relative Radiotoxicity
`
`Physical
`Half-Life,
`days
`
`Specific
`Activity,
`Ci/g
`
`External Gamma
`Dose Rate,
`r [hr at 1 meter
`per curie
`
`Single Inhalation,
`in curies,
`to Give 15 rem
`to Critical Organ,
`Ci/15 rem
`
`Single lnhalalion,
`in curies,
`to Give 15 rem
`to Lung,•
`Ci/15 rem
`
`Group I
`
`Group II
`
`s2Br
`51Cr
`ssFe
`
`Group ID
`,ss
`19sAu
`
`• ' ca
`1321
`141Ce
`M ixed
`
`Fission•
`
`P roducts
`sssr
`
`140L a
`
`9sNb
`
`6szn
`
`ssco
`s9Fe
`
`Group IV
`
`1s 1Hf
`
`14' Pm
`32p
`
`140Ba
`
`,,.Th
`
`s sKr
`
`192Ir
`
`36Cl
`
`91y
`
`1s2Ta
`45Ca
`s 9Sr
`
`t37Cs
`
`6oco
`144Ce
`
`1261 -
`
`4.5 X 103
`2.0 X 106
`
`9.78 X 103
`4.61
`
`< 0.0002
`< 0.01
`
`6.15 X 10· 2
`2.88 X 10· 2
`
`1.5
`27.8
`1.1 X 10 3
`
`1.06 X 106
`9.20 X 104
`2.51 X 103
`
`}
`
`87.l
`2.7
`4.9
`0.097
`32
`
`•
`
`65
`1.68
`35
`245
`72
`45.1
`
`46
`920
`14.3
`12.8
`24.1
`3.9 X 103
`74.5
`1.2 X 108
`58
`112
`164
`50.5
`1.1 X 104
`1.9 x 103
`290
`13.3
`
`4.28 X 104
`2.44 X 105
`5.90 X 105
`1.05 X 107
`2.80 X 104
`
`< 4.00 X l0 1u
`
`2.37 X 104
`5.61 X 105
`3.93 X 104
`8.20 X 103
`3.13 X 104
`4.92 X 104
`
`1.62 X 104
`9.25 X 102
`2.85 X 105
`7.30 X 104
`2.32 X 104
`39.6
`9.16 X 103
`3.21 X 10· 2
`2.50 X 104
`6.20 X 103
`1.77 X 104
`2.77 X 104
`98.5
`1.14 X 103
`3.18 X 103
`7.80 X 104
`
`< 0.01
`0.25
`
`0.95
`
`0,65
`
`< 0.01
`< 0.01
`1.54
`
`0.0019
`0.51
`
`< 0.01
`
`0.36
`1.32
`0.20
`
`7.47 X 10- 3
`8.84 X 10· 2
`2.17 X 10- 3
`
`7.23 X 10 4
`7.25 X 10· 4
`2.59 X 10·4
`4.50 X 10· 4
`7.06 X 10· 4
`
`1.40 X 10· 4
`
`2.00 X 10· 3
`4.20 X 10- •
`3.60 X 10· 3
`2.60 X 10· 4
`8.40 X 10· 3
`3.00 X 10- •
`
`9.94 X 10· 5
`8.90 X 10· 5
`8.70 X 10· 5
`1.40 X 10· 4
`8.50 X 10· 5
`6.90 X 10· 2
`3.20 X 10·•
`2.70 X 10· 3
`5.00 X 10· 5
`1.10 X 10-•
`4.30 X 10· 5
`4.00 X 10·5
`2.60 X 10-4
`2.60 X 10· 3
`1.40 X t0· 5
`1.40 X 10- 5
`
`-
`5.30 X 10· 3
`2.30 X 10· 3
`
`6.90 X 10-•
`5.30 X 10-•
`4.60 X 10-•
`-
`4.20 X 10-•
`
`•
`
`2.70 X to·•
`2.60 X 10-•
`2.30 X 10-•
`I.SO X 10-•
`1.30 X 10- •
`1.30 X 10-•
`
`1.92 X 10-•
`2.30 X 10- •
`2.10 X 10-•
`8.60 X 10- 5
`7.30 X 10· 5
`5.80 X 10- 5
`6.90 X 10·5
`5.30 X 10-5
`7.30 X 10- 5
`5.00 X 10·5
`2.60 X 10-•
`8.50 X 10· 5
`3.00 X 10- 5
`2.20 X 10-5
`1.50 X 10· 5
`7.30 X 10-•
`
`14 of 59
`
`

`

`666
`
`Handbook of Radioactive Nuclides
`
`Table 41. (Continued)
`RADIOTOXICITY VERSUS LEVELS
`ABOVE WHICH VARIOUS SAFEGUARDS MAY BE REQUIRED6
`(See footnotes at end of table.)
`
`Radionuclides
`
`Physical Properties
`
`Relative Radiotoxicity
`
`-
`
`Physical
`Half-Life,
`days
`
`Specific
`Activity,
`Ci/g
`
`External Gamma
`Dose Rate,
`r{hr at 1 meter
`per curie
`
`Single Inhalation,
`in curies,
`to Give 15 rem
`to Critical Organ,
`Ci/ 15 rem
`
`Single Inhalation -
`.
`'
`.
`in curies,
`to Give 15 rem
`to Lung,•
`Ci/ 15 rem
`
`Group IV ( cont.)
`
`IS4£U
`131 I
`I ' °Tm
`
`Group V
`
`Group VI
`
`223Ra
`21op0
`22,Th
`
`9os r
`21opb
`
`242cm
`
`233U
`
`235 U(+ I %
`234U)
`
`n•u +
`Naturalu
`
`232To +
`
`N•turalTh
`
`Group VII
`
`14'Sm
`'44Nd
`226Ra
`
`244cm
`
`Group VIII
`
`243Am
`
`24'Am
`
`23'Np
`22, Ac
`
`23<>'fh
`
`242Pu
`
`2Jspu
`
`240Pu
`
`239Pu
`
`5.8 X 103
`8
`127
`
`1.45 X 102
`1.24 X 105
`6.08 X 103
`
`0.25
`0.004
`
`1.30 X 10- 5
`1.20 X 10- 5
`3.80 X 10-s
`
`1.60 X 10-s
`7.30 X 10- 4
`7.50 X 10-s
`
`6.3 X 10
`
`9 I 1.62 X 10- 4
`
`1.71 X 10- 2
`
`1
`
`2.30 X 10 - 6
`9.10 X 10- 6
`
`1.60 X 10- 4
`
`11.7
`138.4
`18.4
`1.0 X 104
`7.1 X 103
`162.5
`5.9 X 107
`
`2.6 X 1011
`
`5.00 X 104
`4.50 X 103
`3.17 X 104
`1.44 X 102
`88
`3.34 X 103
`0.01 (with
`80 ppm 232 U)
`2.15 X I0- 6
`
`< 0. 00005
`
`< 0.01
`
`< 0.01
`0.0002 (with
`20 ppm 232U)
`< 0.002
`
`3.90 X 10- 6
`1.30 · 10-6
`5.50 X 10- 7
`3.90 X 10 - 7
`3.20 V 10- 1
`3.00 X 10- 7
`7.00 X 10- 7
`
`5.30 X 10- 7
`5.00 X 10- 7
`4.60 X 10- 7
`1.30 X 10-s
`5.30 X 10- 7
`4.60 X 10- 7
`2.70 X 10- 7
`
`1.10 X 10- 6
`
`2.60 X 10- 7
`
`1.6 X 1012
`
`3.34 X 10 - 7
`
`< 0.002
`
`1.90 X 10 - 7
`
`3.00 X 10- 7
`
`5.1 X 1012
`
`l.ll x l0- 7
`
`< 0.0002
`
`2.25 X 10- 9
`
`2.60 X 10-•
`
`4.8 X 1013
`7.3 X 1017
`5.9 X 105
`6.7 X 103
`
`J.95 X 10- 8
`4.97 X 10- 13
`1.00
`82
`
`2.9 X 106
`1.7 X 105
`8.0 X 108
`8.0 X 103
`2.9 X 107
`1.4 X 108
`3.3 X 104
`2.4 X 106
`8.9 X 106
`
`1.85 X 10- 1
`3.21
`6.90 X 10-4
`72
`1.97 X 10- 2
`3.90 X 10- 3
`16.8
`0.227
`0.0617
`
`0.826
`
`0.039
`
`0.009
`
`< 0.02
`< 0.001
`< 0.00001
`
`7.70 X 10-a
`7.70 x 10-•
`4.90 X 10- 8
`1.10 X 10-a
`
`7.60 X 10- 9
`6.60 X 10- 9
`5.20 X 10- 9
`3.00 X 10 - 9
`2.80 X 10- 9
`2.50 X 10- 9
`2.20 X 10- 9
`2.00 X 10- 9
`2.00 X 10- 9
`
`-
`
`6.90 X 10- 7
`7.30 X 10- 7
`1.50 X 10- •
`2.30 X 10- 7
`
`2.70 X 10- 7
`2.70 X 10- 7
`2.70 X 10-'
`6.90 X 10- 8
`2.30 X 10- •
`8.50 X 10- •
`7.30 X 10- •
`8.50 X 10- •
`8.50 X 10-•
`
`15 of 59
`
`

`

`i "' Ct.
`§ ....
`~-g
`~
`
`i
`
`Cl
`
`g.
`~ ;(cid:173)
`
`10 Q2/3
`
`2.2 Q2/3
`2.2 Q2/3
`2.2 Q2/3
`
`0.47 Q213
`0.47 Q2/3
`
`Low-Population
`
`Radius• of
`
`meters
`Zone (X),
`
`Site
`
`Facilities and Equipment
`
`Radionuclides
`
`Table 41. RADIOTOXICITY VERSUS LEVELS ABOVE WHICH VARIOUS SAFEGUARDS MAY BE REQUIRED6 (Continued)
`
`~
`
`10 Q213
`
`104 Ci
`
`10•
`
`102 Ci
`
`102 Ci
`
`0.1 Ci
`
`2Ci
`
`0.1 Ci
`
`10-2ci
`
`1 Ci
`
`1 Ci
`
`4Ci
`
`104 Ci
`
`103
`
`102 Ci
`
`102 Ci
`
`0.1 Ci
`
`0.1 Ci
`
`10-2 Ci
`
`105 Ci
`105 Ci
`105 Ci
`
`106 Ci
`106 Ci
`
`104 Ci
`104 Ci
`104 Ci
`
`105 Ci
`105 Ci
`
`103 C!
`103 Ci
`103 Ci
`
`104 Ci
`104 Ci
`
`103 Ci
`103 Ci
`103 Ci
`
`104 Ci
`104 Ci
`
`Leak Rate'
`or Controlled
`Containment
`
`Building
`
`and Alarm'
`
`Exhaust Stack
`
`Continuous
`
`Monitor
`
`with Alarm•
`Air Sampler
`
`Continuous
`
`General
`
`2 Absolute
`
`in Seriesd
`
`Filters
`
`1 Ci
`1 Ci
`1 Ci
`
`10 Ci
`10 Ci
`
`1 Absolute
`
`Filter<
`
`Inside Hot Cell
`
`Glove Box
`
`or Caveb
`
`1 Ci
`1 Ci
`1 Ci
`
`0.1 Ci
`0.1 Ci
`0.1 Ci
`
`10 Ci
`lOCi
`
`1 Ci
`1 Ci
`
`Group Ill
`
`sspe
`•1cr
`s•Br
`
`Group IT
`
`14c
`3H
`
`Group I
`
`Required
`
`Box
`Glove
`
`Chemical
`
`Required
`
`Hood
`
`}
`
`>9Fe
`51Co
`65Zn
`9sNb
`140La
`sssr
`Products
`Fission•
`Mixed
`•••ce
`1321
`•1ca
`19sAu
`35$
`
`16 of 59
`
`

`

`t ~
`
`f
`Is
`I» !-z
`~ e: 0
`0 ...
`
`220 Ql/3
`220 Q2/l
`
`I
`
`102 Ci
`102 Ci
`
`I
`
`I 10 Ci
`
`10 Ci
`
`I I Ci
`
`1 Ci
`
`l Ci
`1 Ci
`
`I 10-3 Ci I
`
`10-•ci
`
`47 Q213
`
`103 Ci
`
`IO~ Ci
`•
`
`IO Ci
`
`IOCi
`
`10 2 Ci
`
`Ci I
`
`10-3 Ci
`
`3
`
`\ 10-
`
`10-4 Ci
`Ci
`
`\ 10-
`
`4
`
`250Ci
`4Ci
`
`5 Ci
`1 Ci
`3 Ci
`
`IOOCi
`
`2Ci
`500 Ci
`
`0.5 Ci
`
`100 Ci
`lOOCi
`
`10-2 Ci
`
`10-3 Ci
`
`47 Q2/l
`
`103 Ci
`
`102 Ci
`
`10 Ci
`
`10 Ci
`
`10-2ci
`
`10-2 Ci
`
`10-3 Ci
`
`99Tc
`
`1291
`
`Group V
`
`170,-m
`
`1311
`,,.Eu
`1261
`144Ce
`6oco
`i37cs
`89Sr
`45Ca
`
`u2Ta
`
`91y
`J6CI
`u21r
`s,Kr
`234Th
`"oBa
`32p
`t47Pm
`
`•••ttr
`
`Group IV
`
`Low-Population
`
`Radius• of
`
`meters
`Zone (X),
`
`Leak Rate'
`or Controlled
`Containment
`
`Building
`
`Exhaust Stack
`
`Continuous
`
`and Alarm'
`
`Monitor
`
`with Alarm•
`Air Sampler
`
`Continuous
`
`General
`
`2 Absolute
`
`in Series•
`
`Filters
`
`I Absolute
`
`Filter0
`
`Inside Hot Cell
`
`Glove Box
`
`or Caveb
`
`Required Required
`
`Box
`Glove
`
`Chemical
`
`Hood
`
`Site
`
`Facilities and Equipment
`
`Radionuclides
`
`i
`
`Table 41. RADIOTOXICITY VERSUS LEVELS ABOVE WHICH VARIOUS SAFEGUARDS MAY BE REQUIRED6 (Continued)
`
`17 of 59
`
`

`

`$
`
`f
`i
`i
`l ::I
`
`g
`§..
`~ e:
`
`4,700 Q2l3
`
`4,700 Q213
`
`l
`
`l
`
`1 Ci
`
`1 Ci
`
`0.1 Ci
`
`l
`
`0.1 Ci
`
`10-2 Ci
`
`l
`
`10-2 Ci
`
`10-2 Ci
`
`l
`
`10-2 Ci
`
`1
`
`10-5 Ci
`
`10-5 Ci
`
`1
`
`10-5 Ci
`
`10-sci
`
`10-6 Ci
`
`\ 10-t
`
`244Cm
`226Ra
`144Nd
`14'Sm
`
`1,000 Q2/3
`
`JO Ci
`
`1 Ci
`
`0.1 Ci
`
`0.1 Ci
`
`10-5 Ci
`
`10-4 Ci
`
`10-6 Ci
`
`1,000 Q2/3
`
`10 Ci
`
`1 Ci
`
`0.1 Ci
`
`0.1 Ci
`
`10-4ci
`
`10-4 Ci
`
`10-5 Ci
`
`(500 kg)
`
`5,000 Ci
`100 Ci
`
`100 Ci
`
`20,000 Ci
`
`Group VII
`
`N•turalTh
`232Th+
`NaturalU
`23au+
`
`234U)
`235U(+l¼
`
`233u
`242cm
`21opb
`9osr
`22,Th
`21opo
`223Ra
`
`Group VI
`
`Low-Population
`
`Radius• of
`
`meters
`Zone (X),
`
`Leak Rater
`or Controlled
`Exhaust Stack Containment
`
`Building
`
`Continuous
`
`and Alarmr
`
`Monitor
`
`with Alarm•
`Air Sampler
`
`Continuous
`
`General
`
`2 Absolute
`
`in Seriesd
`
`Filters
`
`1 Absolute
`
`Filter•
`
`Inside Hot Cell
`
`Glove Box
`
`or Caveb
`
`Required Required
`
`Box
`Glove
`
`Chemical
`
`Hood
`
`Site
`
`Facilities and Equipment
`
`Radionuclides
`
`TabJe 41. RADIOTOXICITY VERSUS LEVELS ABOVE WHICH VARIOUS SAFEGUARDS MAY BE REQUIRED6 (Continued)
`
`18 of 59
`
`

`

`:,:-
`0
`0
`0'
`Q.
`~
`::i::
`
`f
`!:?.
`~ z C
`~~
`;:i::, e: 0 .,
`0 ...
`
`JO Ci
`JO Ci
`
`106 Ci
`106 Ci
`
`l04Ci
`104 Ci
`
`103 Ci
`103 Ci
`
`Maximum Credible
`
`Accidents
`
`Preoperational
`
`Written
`
`Analysis of
`
`Procedures
`Operating
`Routine
`Written
`
`and Drills
`Procedures
`Emergency
`
`Preplanned
`
`Written
`
`and Community
`
`Environmental
`
`Routine
`
`Monitoring
`
`of Site
`
`High External
`
`Doses
`
`Dosimeters
`Emergency
`
`Procedures
`
`22,000 Q213
`
`0.1 Ci
`
`10-2 Ci
`
`10-3 Ci
`
`10-3 Ci
`
`22,000 Q2/3
`
`0.1 Ci
`
`10-2 Ci
`
`10-3 Ci
`
`10-3 Ci
`
`Exhaust Stack Containment Low-Population
`
`meters
`Zone (X),
`
`Leak Rate1
`or Controlled
`
`Radius• of
`
`Building
`
`and Alarm1
`Monitor
`
`Continuous
`
`with Alarm•
`Air Sampler
`
`Continuous
`
`General
`
`2 Absolute
`
`in Seriesd
`
`Filters
`
`Site
`
`::l
`
`Q
`
`(Continued)
`
`102 Ci
`102 Ci
`
`10 Ci
`10 Ci
`
`\
`
`\
`
`uc
`JH
`
`Group I
`
`Worn to Measure
`
`Excretion Assay
`
`Routine
`
`Personnel
`Operating
`
`of All
`
`Excretion Radioassay
`
`Occasional
`
`of Operating
`Spot Checks
`
`Personnel
`
`Shielding vs. External
`
`and/or Appropriate
`Personnel Monitoring
`
`Gamma Radiation
`
`Table 41. RADIOTOXICITY VERSUS LEVELS ABOVE WHICH VARIO US SAFEGUARDS MAY BE REQUIRED6 (Continued)
`
`Radionuclides
`
`10-6 Ci
`
`1,000 Cit
`
`10-6 Ci
`
`10-1 Ci
`
`SO Ci
`
`lOOCi
`
`25 Ci
`
`10-6 Ci
`
`10-6 Ci
`
`10-7 Ci
`
`239Pu
`
`24opu
`
`23Bpu
`
`242Pu
`
`230Th
`
`,21Ac
`
`237Np
`
`24'Am
`
`243Am
`
`Group VIII
`
`Inside Hot Cell 1 Absolute
`
`Filter0
`
`or Caveb
`
`Glove Box
`
`Required Required
`
`Box
`Glove
`
`Chemical
`
`Hood
`
`Table 41. RADIOTOXICITY VERSUS LEVELS ABOVE WHICH VARIOUS SAFEGUARDS MAY BE REQUIRED6
`
`Facilities and Equipment
`
`Radionuclides
`
`19 of 59
`
`

`

`6 ,.
`
`0 = "'0
`"' ::t.
`"' e:
`
`';Q
`
`§
`
`0 = "'
`C:
`£;'
`~
`;;i:,
`
`"' = i:,..
`=
`
`0.1 Ci
`
`104 Ci
`
`102 Ci
`
`JO Ci
`
`20 Ci
`
`I Ci
`
`0.1 Ci
`
`0.20 Ci
`
`0.1 Ci
`
`104 Ci
`
`102 Ci
`
`10 Ci
`
`I Ci
` Ci
`1 Ci
`
`.I
`
`J05 Ci
`J05 Ci
`105 Ci
`
`IOJ
`JOl
`JOJ
`
`102 Ci
`102 Ci
`102 Ci
`
`10 Ci
`
`40Ci
`
`50 Ci
`
`l Ci
`
`0.1 Ci
`
`lOCi
`IOCi
`10 Ci
`
`I Ci
`l Ci
`l Ci
`
`IOCi
`
`O.
`
`0.40 Ci
`
`0.50 Ci
`
`Mixed )
`
`s9Fe
`ssco
`6szn
`9'Nb
`140La
`sssr
`Products
`Fission*
`
`14,Ce
`1321
`
`47Ca
`19sAu
`3ss
`
`Group Ill
`
`55Fe
`s1cr
`s2Br
`
`Group II
`
`Maximum Credible
`
`Accidents
`
`Preoperational
`
`Written
`
`Analysis of
`
`and Drills
`Procedures
`Procedures Operating
`Emergency
`Routine
`Written
`
`Written
`
`Preplanned
`
`and Community
`
`Environmental
`
`Routine
`
`Monitoring
`
`of Site
`
`Worn to Measure
`
`High External
`
`Doses
`
`Dosimeters
`Emergency
`
`Personnel
`Operating
`
`of All
`
`Routine
`
`Excretion Radioassay Excretion Assay
`
`of Operating
`Spot Checks
`
`Personnel
`
`Occasional
`
`Shielding vs. External
`and/or Appropriate
`Personnel Monitoring
`
`Gamma Radiation
`
`Table 41. RADIOTOXICITY VERSUS LEVELS ABOVE WHICH VARIOUS SAFEGUARDS MAY BE REQUIRED6 (Continued)
`
`Procedures
`
`Radionuclides
`
`20 of 59
`
`

`

`~ ~ I
`I 2, J
`
`10-5 Ci
`10-3 Ci
`
`102 Ci
`102 Ci
`
`1 Ci
`1 Ci
`
`0.1 Ci
`0.1 Ci
`
`10,000 Ci
`
`10-2 Ci
`10-2 Ci
`
`10-3 Ci
`10-3 Ci
`
`10-2 Ci
`
`103 Ci
`
`10 Ci
`
`1 Ci
`
`2,500 Ci
`40Ci
`
`5 Ci
`lOCi
`30 Ci
`
`1,000 Ci
`
`20Ci
`5,000 Ci
`
`5 Ci
`1,000 Ci
`1,000 Ci
`
`0.1 Ci
`
`10-2ci
`
`10-2 Ci
`
`103 Ci
`
`10 Ci
`
`1 Ci
`
`0.1 Ci
`
`10-2 Ci
`
`100.00 Ci
`
`\
`
`99Tc
`
`1291
`
`Group V
`
`25.00 Ci
`0.40Ci
`
`0.05 Ci
`0.10 Ci
`0.30 Ci
`
`10.00 Ci
`
`0.Q2Ci
`50.00 Ci
`
`0.05 Ci
`10.00 Ci
`10.00