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calculation of doses due to accidentally 1 b released plutonium from an lmf8.r nuclear safety PDF

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Preview calculation of doses due to accidentally 1 b released plutonium from an lmf8.r nuclear safety

;ORNL-NSIC-74 CALCULATION OF DOSES DUE TO ACCIDENTALLY 1 B RELEASED PLUTONIUM FROM AN LMF8.R B. R. Fish, G. W. Keilholtz, W. S. Snyder, S. D. Swisher NSlC NUCLEAR SAFETY INFORMATION CENTER ORNL-NSIC-74 Contract No. W-7405-eng-26 Nuclear Safety Information Center CALCULATION OF DOSES DUE TO ACCIDENTALLY RELEASED PLUTONIUM FROM AN LMFBR B. R. Fish, Health Physics Division G. W. Keilholtz, Reactor Chemistry Division W. S.. Snyder, Health Physics Division S; D. Swisher, Atmospheric Turbulence and Diffusion Laboratory, NOAA NOVEMBER 1972 OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37830 operated by UNION CARBIDE CORPORATION for the U.S. ATOMIC ENERGY COMMISSION Printed in the United States of America. Available from National Technical Information Service U.S. Department of Commerce 5285 Port Royal Road, Springfield, Virginia 22151 Price: Printed Copy $15.00; Microfiche $15.00 This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the United States Atomic Energy Commission, nor any ‘of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not infringe privately owned rights. iii CONTENTS c Page PREFACE ............................................................. V ‘4 ACKNOWLEDGMENT.. .................................................... vii ABSTRACT ............................................. .. .............. ix 1. INTRODUCTION .................................................... 1 2. BEHAVIOR OF RELEASED SODIUM OXIDE AND PLUTONIUM- BEARING PARTICLES ..;............................................ 4 2.1 Aerosol Behavior Considerations . . . . . . . . . . . . . . . . . . . . . . . . . . . . ,2.1.1 Brownian motion _.................................... 2.1.2 Gravity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1.3 Turbulence . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.2 Experimental Evidence for Decay of Mass Concentration and Changes in Particle Size of Airborne Aerosols with Time ....................................................... 10 2.3 Empirical Models and Equations for the Decay of Mass Con- centration and Changes in Particle Size with Time .......... 12 2.3.1 Schikarski model .................................... 13 2.3.2 Davis model ..... ..................................... 14 2.3.3 Koontz model ........................................ 15 2.4 Detailed Discussion of an Aerosol Model and Its Appli- cation ..................................................... 16 2.5 A Postulated Release of Radionuclides from an LMFBR- Type Reactor under Accident Conditions ..................... 24 t References ...................................................... 27 3. TRANSPORT, SETTLING, AND REDISTRIBUTION OF AEROSOLS IN THE ouTsIDE Am (TROPOSPHERE) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31 3.1 Meteorological Considerations .............................. 31 3.2 Properties of NazO Aerosols in the Atmosphere .............. 32 References ...................................................... 35 4. CHEMISTRY OF PLUTONIUM .......................................... 36 4.1 Compounds of Plutonium ..................................... 36 4.1.1 Plutonium dioxide and mixed oxides .................. 37 4.1.2 Plutonium carbides, nitrides, and silicides ......... 44 4.1.3 Sodium-uranium-plutonium oxides ..................... 45 4.1.4 Other inorganic compounds ........................... 45 4.2 Solution Chemistry of Plutonium ............................ 46 4.2.1 Complex formation by plutonium in aqueous solutions ........................................... 47 4.2.2 Solubility of plutonium compounds ................... 49 4.2.3 Complex formation by plutonium in various oxida- tion states .......................................... 50 4.3 Methods for Separation of Plutonium from Uranium and Fission Products ........................................... 52 4.3.1 Solvent extraction .................................. 52 4.3.2 Ion exchange methods ................................ 53 iv 4.4 Analytical Methods for Determining Plutonium ............... 55 4.4.1 Conventional methods ................................ 55 4.4.2 Radiochemical methods ............................... 56 References ...................................................... 57 5. INTAKE AtiD METABOLISM OF PLUTONIUM DIOXIDE ...................... 60 5.1 Intake Pathways ............................................ 61 5.1.1 Inhalation .......................................... 61 5.1.2 Ingestion ........................................... 77 5.1.3 Deposition on body surfaces ......................... 84 5.2 Systemic Distribution and Retention ........................ 86 5.2.1 Transport in the bloodstream ........................ 86 5.2.2 Deposition and retention in bone .................... 87 5.2.3 Deposition and retention in liver ................... 88 5.2.4 Deposition and retention in gonads .................. 89 5.2.5 Elimination of plutonium from the body .............. 90 References ...................................................... 93 6. COMPUTATION OF INTERNAL DOSE .................................... 104 6.1 Physical Dosimetry and Dose Equivalent ..................... 104 6.2 Dose Calculations for Inhaled Plutonium .................... 106 6.3 Consideration of Other Plutonium Isotopes .................. 110 6.4 Consideration of Other Transuranics ........................ 113 6.5 Gastrointestinal Tract Intake During Release ............... 116 6.6 Ingestion of Plutonium in Food.and Water ................... 117 6.7 Summary Calculations ....................................... 117 6.7.1 Source term evaluations ............................. 117 6.7.2 Leakage and dispersion .............................. 119 6.7.3 Calculation of dose ................................. 119 References ....................................................... 121 7. SUMMARY ......................................................... 122 . V PREFACE The Nuclear Safety Information Center, established in March 1963 at the Oak Ridge National Laboratory under the sponsorship of the U.S. Atomic Energy Commission, is a focal point for the collection, storage, evalu- ation, and dissemination of nuclear safety information. A system of key words is used to index the information cataloged by the Center. The title, author, installation, abstract, and key words for each document reviewed are recorded at the central computer facility in Oak Ridge. The references are cataloged according to the following categories: 1. General Safety Criteria 2. Siting of Nuclear Facilities 3. Transportation and Handling of Radioactive Materials 4. Aerospace Safety 5. Heat Transfer and Thermal Transients 6. Reactor Transients, Kinetics, and Stability 7. Fission Product Release, Transport, and Removal 8. Sources of Energy Release under Accident Conditions 9. Nuclear Instrumentation, Control, and Safety Systems 1-O. Electrical Power Systems 11. Containment of Nuclear Facilities 12. Plant Safety Features - Reactor 13. Plant Safety Features - Nonreactor 14. Radionuclide Release and Movement in the Environment 15. Environmental Surveys, Monitoring, and Radiation Exposure of Man 16. Meteorological Considerations 17. Operational Safety and Experience 18. Safety Analysis and Design Reports 19. Radiation Dose to Man from Radioactivity Release to the Environment 20. Effects of Thermal Modifications on Ecological Systems 21. Effects of Radionuclides and Ionizing Radiation on Ecological Systems vi Computer programs have been developed which enable NSIC to (1) oper- ate a routine program of Selective Dissemination of Information (SDI) to . individuals according to their particular profile of interest, (2) make retrospective searches of the stored references, and (3) distribute scope and progress information on R&D contracts from the Program and Project In- formation File (PPIF). Services of the NSIC are available to government agencies, research and educational institutions, and the nuclear industry on a partial cost recovery basis designed to regain a portion of the expense associated with disseminating the information to the user. A minimal inquiry response is available free. NSIC reports (i.e., those with the ORNL-NSIC numbers) may be purchased from the National Technical Information Service (see inside front cover) while documents indexed by NSIC may be examined at the Center by qualified personnel. Inquiries concerning the capabilities and oper- . ation of the Center may be addressed to: J. R. Buchanan, Assistant Director (Phone 615-483-8611, Ext. 3-7253) Nuclear Safety Information Center Oak Ridge National Laboratory Post Office Box Y Oak Ridge, Tennessee 37830 vii ACKNOWLEDGMENT 2 In the preparation of this report the authors benefitted from the review and comment of many people who are active in various aspects of the many fields of expertise involved in accident analysis and plutonium dose calculation. While this does not mean that all reviewers necessa- rily agree with the report in every detail, we do wish to acknowledge their contribution by listing the participants. .Trusting that no one has been overlooked, they are as follows: Internal Reviewers (ORNL) C. J. Barton Wm. B. Cottrell F. L. Miller S. R. Bernard R. J. Davis P. Nettesheim R. H. Bryan P. B. Dunaway G. W..Parker T. J. Burnett M. H. Fontana L. F. Parsly J. R. Buchanan A. P. Malinauskas H. B. Piper P External Reviewers i A. W. Castleman, Brookhaven National Laboratory Patricia W. Durbin, Lawrence Berkeley Laboratory Headquarters Staff, U.S. Atomic Energy Commission M. M. Hendrickson, Battelle-Northwest Laboratories H. H. Hopkins, Atlantic Richfield, Hanford Company R. L. Junkins, Battelle-Northwest Laboratories W. H. Langham (deceased), Los Alamos Scientific Laboratory J. N. P. Lawrence, Los Alamos Scientific Laboratory H. E. Meyer, Mound Laboratory H. A. Morewitz, Atomics International I. Nelson, Battelle-Northwest Laboratories W. D. Norwood, Hanford Environmental Health Foundation L. C. Schwendiman, Battelle-Northwest Laboratories R. C. Thompson, Battelle-Northwest Laboratories

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oxides of uranium and plutonium as fuel has been treated Chapter 4 reviews the chemical properties of plutonium. mal gradient, accentuating A. Aitken and S. K. Evans, A Thermodynamic Data Program In- volving Plutonia.
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