Practical Aspects of Operating a Neutron Activation Analysis Laboratory

Total Page:16

File Type:pdf, Size:1020Kb

Practical Aspects of Operating a Neutron Activation Analysis Laboratory IAEA-TECDOC-564 PRACTICAL ASPECTS OF OPERATING A NEUTRON ACTIVATION ANALYSIS LABORATORY A TECHNICAL DOCUMENT ISSUED BY THE INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 1990 PRACTICAL ASPECT OPERATINF SO G A NEUTRON ACTIVATION ANALYSIS LABORATORY IAEA, VIENNA, 1990 IAEA-TECDOC-564 ISSN 1011-4289 Printe IAEe th AustriAn i y d b a July 1990 PLEASE BE AWARE THAT MISSINE TH AL F LO G PAGE THIN SI S DOCUMENT WERE ORIGINALLY BLANK FOREWORD This boo s intendei k o advist d n everydai e y practical problems relateo t d operating a neutron activation analysis (NAA) laboratory. It gives answers to questions like "what to use NAA for", "how to find relevant research problems", "how to find users for the technique", "how to estimate the cost of the analysis and how to finance the work", "how to organize the work in a rational way d "ho"an o perforwt e qualitth m y control" givet I . s advice in choosing staff, equipment d consumableo desigt an , w nho facilitied an s s and procedures accordin neeo d availablt g an d e resources. e boo Th s designei k o discust d s problem t dealno s t wit n ordinari h A NA y textbooks, but also, in order to prevent it from being too voluminous, to avoid duplication of material described in normal NAA text books. Therefore e readeth , r will find that some materia f intereso l missins i t g from this book and it is recommended that one or two of the textbooks listed in chapter 11 be read in addition to this one. e authorTh s represen a widt e rang f o experience e with biological, environmental, geological d industriaan , l samples n contexti , s from basic research to commercial analytical service. Their backgrounds also range from universit o governmentat y l research institut d privatan e e enterprise. Their summed experience exceed e timth se since Heves d Levy'an y s first publication on activation analysis; nevertheless, other workers in the field may not agree with all the statements made herein. It is their hope that this publication will be of value, both in respect to practical aspects of running a modern NAA laboratory, and in recommending relevant application a tim n ei s with abundant analytical techniquea d an s requiremen well-foundea r tfo d cost/benefi activitiesl t al rati r fo o . EDITORIAL NOTE In preparing this material press,the for staff Internationalofthe Atomic Energy Agency have mounted paginatedand originalthe manuscripts givenand some attention presentation.to The views expressed necessarilynot do reflect those governments ofthe Member ofthe States or organizations under whose auspices the manuscripts were produced. The use in this book 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 institutions delimitationand the of or theirof boundaries. The mention specificof companies theirof or products brandor names does implynot any endorsement or recommendation on the part of the IAEA. CONTENTS 1. INTRODUCTION ..................................................................................... 7 . 2 PRINCIPLE INSTRUMENTAF SO L NEUTRON ACTIVATION ANALYSIS ...........9 . 2.1. Historical background ............................................................................9 . 2.2. Characteristic f neutroo s n activation analysis ................................................9 . 2.3. Sensitivities available with NAA .............................................................. 18 . 3 POTENTIAL APPLICATION ECONOMIF SO SOCIAD CAN L IMPORTANCE ......0 2 . 3.1. Major applications ................................................................................ 20 3.2. Other applications ...............................................................................9 2 . 4. IRRADIATION FACILITIES ........................................................................ 33 4.1. Research reactor types ..........................................................................3 3 . 4.2. Sample encapsulation ............................................................................ 37 4.3. Irradiation sites ...................................................................................3 4 . 4.4. Irradiation in modified flux ..................................................................... 47 . 5 COUNTIN DATD GAN A PROCESSING FACILITIES ......................................0 5 . 5.1. Typical counting systems .......................................................................0 5 . 5.2. Semiconductor detectors ......................................................................... 51 5.3. Basic electronics .................................................................................5 6 . 5.4. Multichannel pulse height analyzer (MCA) ................................................. 81 5.5. Data processing ..................................................................................5 8 . 5.6. Automation ........................................................................................8 8 . 5.7. Choic f locatioeo n ...............................................................................3 9 . 6. RELATED TECHNIQUES ..........................................................................6 9 . 6.1. Delayed neutron activation analysis ..........................................................6 9 . 6.2. Prompt gamma neutron activation analysis .................................................. 99 6.3. Measurement of environmental radioactivity ................................................ 99 7. MAKING NAA AVAILABLE TO THE SCIENTIFIC AND TECHNICAL COMMUNITY ......................................................................1 10 . 7.1. Identification of possible consumers .......................................................... 101 7.2. Collecting background informatio identificatiod nan f applicationno s .................4 10 . 7.3. Consultation with potential consumers ....................................................... 104 7.4. Mode f providino s serviceA gNA s ..........................................................5 10 . 7.5 Cost analysis ...................................................................................... 108 . 8 ORGANIZATIO WORF NO K ......................................................................5 11 . 8.1. Staff ................................................................................................5 11 . 8.2. Sample bookkeeping and coding .............................................................. 116 8.3. Sample preparation ..............................................................................9 11 . 8.4. Standards ........................................................................................... 126 8.5. Irradiation procedures ........................................................................... 128 8.6. Decay ..............................................................................................6 13 . 8.7. Measurements ....................................................................................8 13 . 8.8. Data processing ..................................................................................8 14 . 8.9. Reporting ........................................................................................... 150 . 9 QUALITY ASSURANCE ............................................................................6 15 . 9.1. Nee r qualitdfo y assurance ....................................................................6 15 . 9.2. Methods for quality assurance ................................................................. 156 9.3. Assignement of uncertainty ..................................................................... 161 9.4. Location of sources of errors .................................................................. 163 10. RADIATION PROTECTION ........................................................................ 169 11. SUGGESTED READING ............................................................................. 172 REFERENCES ................................................................................................. 175 APPENDIX A. TABLES FOR NEUTRON ACTIVATION ANALYSIS ......................... 193 Introduction .............................................................................................3 19 . Reference Introductioo t s n ...........................................................................6 19 . Table I. Thermal neutron cross-sections and resonance integrals .......................... 197 Table II. Cross-sections averaged in a 235U fission neutron spectrum ..................... 202 Table III. Radioactive isotopes arranged by atomic number .................................. 203 Tabl . GammeIV a rays arrange energy db y day 1 (t, < /)2 ..................................1 22 . Table V. Gamma rays arranged by energy (t1/2 > Iday) .................................... 228 Tabl . RecommendeeVI d gamma ray r analysifo s theid an s r interferences hours5 (t, /< 2 ) ..........................................................................8 23 . Table VII. Recommended gamma ray r analysifo s theid an s r interferences (5 hour days7 t< s1/ < 2) .............................................................0 24 . Table VIII. Recommended gamma rays for analysis and their interferences (t1/2 > 7 days) ............................................................................ 243 Reference tableo t s s ...................................................................................8
Recommended publications
  • Neutron Interactions and Dosimetry Outline Introduction Tissue
    Outline • Neutron dosimetry Neutron Interactions and – Thermal neutrons Dosimetry – Intermediate-energy neutrons – Fast neutrons Chapter 16 • Sources of neutrons • Mixed field dosimetry, paired dosimeters F.A. Attix, Introduction to Radiological • Rem meters Physics and Radiation Dosimetry Introduction Tissue composition • Consider neutron interactions with the majority tissue elements H, O, C, and N, and the resulting absorbed dose • Because of the short ranges of the secondary charged particles that are produced in such interactions, CPE is usually well approximated • Since no bremsstrahlung x-rays are generated, the • The ICRU composition for muscle has been assumed in absorbed dose can be assumed to be equal to the most cases for neutron-dose calculations, lumping the kerma at any point in neutron fields at least up to 1.1% of “other” minor elements together with oxygen to an energy E ~ 20 MeV make a simple four-element (H, O, C, N) composition Neutron kinetic energy Neutron kinetic energy • Neutron fields are divided into three • Thermal neutrons, by definition, have the most probable categories based on their kinetic energy: kinetic energy E=kT=0.025eV at T=20C – Thermal (E<0.5 eV) • Neutrons up to 0.5eV are considered “thermal” due to simplicity of experimental test after they emerge from – Intermediate-energy (0.5 eV<E<10 keV) moderator material – Fast (E>10 keV) • Cadmium ratio test: • Differ by their primary interactions in tissue – Gold foil can be activated through 197Au(n,)198Au interaction and resulting biological effects
    [Show full text]
  • Neutron Activation and Prompt Gamma Intensity in Ar/CO $ {2} $-Filled Neutron Detectors at the European Spallation Source
    Neutron activation and prompt gamma intensity in Ar/CO2-filled neutron detectors at the European Spallation Source E. Diana,b,c,∗, K. Kanakib, R. J. Hall-Wiltonb,d, P. Zagyvaia,c, Sz. Czifrusc aHungarian Academy of Sciences, Centre for Energy Research, 1525 Budapest 114., P.O. Box 49., Hungary bEuropean Spallation Source ESS ERIC, P.O Box 176, SE-221 00 Lund, Sweden cBudapest University of Technology and Economics, Institute of Nuclear Techniques, 1111 Budapest, M}uegyetem rakpart 9. dMid-Sweden University, SE-851 70 Sundsvall, Sweden Abstract Monte Carlo simulations using MCNP6.1 were performed to study the effect of neutron activation in Ar/CO2 neutron detector counting gas. A general MCNP model was built and validated with simple analytical calculations. Simulations and calculations agree that only the 40Ar activation can have a considerable effect. It was shown that neither the prompt gamma intensity from the 40Ar neutron capture nor the produced 41Ar activity have an impact in terms of gamma dose rate around the detector and background level. Keywords: ESS, neutron detector, B4C, neutron activation, 41Ar, MCNP, Monte Carlo simulation 1. Introduction Ar/CO2 is a widely applied detector counting gas, with long history in ra- diation detection. Nowadays, the application of Ar/CO2-filled detectors is ex- tended in the field of neutron detection as well. However, the exposure of arXiv:1701.08117v2 [physics.ins-det] 16 Jun 2017 Ar/CO2 counting gas to neutron radiation carries the risk of neutron activa- tion. Therefore, detailed consideration of the effect and amount of neutron ∗Corresponding author Email address: [email protected] (E.
    [Show full text]
  • TUTORIAL on NEUTRON PHYSICS in DOSIMETRY S. Pomp1
    TUTORIAL ON NEUTRON PHYSICS IN DOSIMETRY S. Pomp1,* 1 Department of physics and astronomy, Uppsala University, Box 516, 751 20 Uppsala, Sweden. *Corresponding author. E‐mail address: [email protected] (S.Pomp) Abstract: Almost since the time of the discovery of the neutron more than 70 years ago, efforts have been made to understand the effects of neutron radiation on tissue and, eventually, to use neutrons for cancer treatment. In contrast to charged particle or photon radiations which directly lead to release of electrons, neutrons interact with the nucleus and induce emission of several different types of charged particles such as protons, alpha particles or heavier ions. Therefore, a fundamental understanding of the neutron‐nucleus interaction is necessary for dose calculations and treatment planning with the needed accuracy. We will discuss the concepts of dose and kerma, neutron‐nucleus interactions and have a brief look at nuclear data needs and experimental facilities and set‐ups where such data are measured. Keywords: Neutron physics; nuclear reactions; kerma coefficients; neutron beams; Introduction Dosimetry is concerned with the ability to determine the absorbed dose in matter and tissue resulting from exposure to directly and indirectly ionizing radiation. The absorbed dose is a measure of the energy deposited per unit mass in the medium by ionizing radiation and is measured in Gray, Gy, where 1 Gy = 1 J/kg. Radiobiology then uses information about dose to assess the risks and gains. A risk is increased probability to develop cancer due to exposure to a certain dose. A gain is exposure of a cancer tumour to a certain dose in order to cure it.
    [Show full text]
  • Conceptual Design Report Jülich High
    General Allgemeines ual Design Report ual Design Report Concept Jülich High Brilliance Neutron Source Source Jülich High Brilliance Neutron 8 Conceptual Design Report Jülich High Brilliance Neutron Source (HBS) T. Brückel, T. Gutberlet (Eds.) J. Baggemann, S. Böhm, P. Doege, J. Fenske, M. Feygenson, A. Glavic, O. Holderer, S. Jaksch, M. Jentschel, S. Kleefisch, H. Kleines, J. Li, K. Lieutenant,P . Mastinu, E. Mauerhofer, O. Meusel, S. Pasini, H. Podlech, M. Rimmler, U. Rücker, T. Schrader, W. Schweika, M. Strobl, E. Vezhlev, J. Voigt, P. Zakalek, O. Zimmer Allgemeines / General Allgemeines / General Band / Volume 8 Band / Volume 8 ISBN 978-3-95806-501-7 ISBN 978-3-95806-501-7 T. Brückel, T. Gutberlet (Eds.) Gutberlet T. Brückel, T. Jülich High Brilliance Neutron Source (HBS) 1 100 mA proton ion source 2 70 MeV linear accelerator 5 3 Proton beam multiplexer system 5 4 Individual neutron target stations 4 5 Various instruments in the experimental halls 3 5 4 2 1 5 5 5 5 4 3 5 4 5 5 Schriften des Forschungszentrums Jülich Reihe Allgemeines / General Band / Volume 8 CONTENT I. Executive summary 7 II. Foreword 11 III. Rationale 13 1. Neutron provision 13 1.1 Reactor based fission neutron sources 14 1.2 Spallation neutron sources 15 1.3 Accelerator driven neutron sources 15 2. Neutron landscape 16 3. Baseline design 18 3.1 Comparison to existing sources 19 IV. Science case 21 1. Chemistry 24 2. Geoscience 25 3. Environment 26 4. Engineering 27 5. Information and quantum technologies 28 6. Nanotechnology 29 7. Energy technology 30 8.
    [Show full text]
  • Sonie Applications of Fast Neutron Activation Analysis of Oxygen
    S E03000182 CTH-RF- 16-5 Sonie Applications of Fast Neutron Activation Analysis of Oxygen Farshid Owrang )52 Akadenmisk uppsats roir avliiggande~ av ilosofie ficentiatexamen i Reaktorf'ysik vid Chalmer's tekniska hiigskola Examinator: Prof. Imre PiAst Handledare: Dr. Anders Nordlund Granskare: Bitr. prof. G~iran Nyrnan Department of Reactor Physics Chalmers University of Technology G6teborg 2003 ISSN 0281-9775 SOME APPLICATIONS OF FAST NEUTRON ACTIVATION OF OXYGE~'N F~arshid Owrang Chalmers University of Technology Departmlent of Reactor Physics SEP-1-412 96 G~iteborg ABSTRACT In this thesis we focus on applications of neutron activation of oxygen for several purposes: A) measuring the water level in a laboratory tank, B) measuring the water flow in a pipe system set-up, C) analysing the oxygen in combustion products formed in a modern gasoline S engine, and D) measuring on-line the amount of oxygen in bulk liquids. A) Water level measurements. The purpose of this work was to perform radiation based water level measurements, aimed at nuclear reactor vessels, on a laboratory scale. A laboratory water tank was irradiated by fast neutrons from a neutron enerator. The water was activated at different water levels and the water level was decreased. The produced gamma radiation was measured using two detectors at different heights. The results showed that the method is suitable for measurement of water level and that a relatively small experimental set-up can be used for developing methods for water level measurements in real boiling water reactors based on activated oxygen in the water. B) Water flows in pipe.
    [Show full text]
  • Neutron Effects on Living Things
    also negotiating an agreement with the Commission International Confederation of Free Trade for Technical Co-operation in Africa. Unions International Co-operative Alliance In addition the Agency has granted consultative International Council of Scientific Unions status to nineteen non-governmental organizations, International Federation of Christian Trade and is considering applications from a number of Unions others. The nineteen are as follows: International Federation of Documentation International Federation of Industrial European Atomic Forum Producers of Electricity for Own European Confederation of Agriculture Consumption International Air Transport Association International Organization for Standardization International Cargo Handling Co-ordination International Union of Inland Navigation Association International Union of Producers and International Chamber of Commerce Distributors of Electrical Energy International Commission on Radiological Japan Industrial Forum Protection World Federation of United Nations International Committee on Radiological Associations Units and Measurements World Power Conference NEUTRON EFFECTS ON LIVING THINGS Scientific interest in neutrons and protons - two Although much has been learned about X-ray fundamental particles of the atomic nucleus - has and gamma-ray effects, comparatively little is known grown in recent years as the technology of peaceful about the biological effects of neutrons, and therefore uses of atomic energy has progressed. Such interest many of the Symposium papers reviewed
    [Show full text]
  • Photon, Neutron, Proton, Electron, Gamma Ray, Carbon Ion)
    Fundamental types of radiation particle beams (Photon, Neutron, Proton, Electron, Gamma Ray, Carbon Ion) Photon This is the most common, widely used type of radiation, and is available at most treatment centers and hospitals. This is widely used to treat most cancers including known or suspect residual ACC which was not able to be removed with surgery by itself. In simple terms, it is fundamentally a very high dose X-ray beam. This is also the type of radiation beam utilized for most of the pinpoint targeted types of radiation treatments, such as CyberKnife, TomoTherapy and Novalis. Most hospitals have photon radiation available and the beam is generated by a beam accelerator device that takes up the space of a typical bedroom. Some of the newer manufacturers have developed a more compact beam accelerator, such as the CyberKnife. Neutron Neutron radiation therapy is a unique, high-LET radiation (the particles are accelerated at a very fast rate) with very specific differences in how it affects DNA in ACC cancer cells when compared to standard Photon radiation. Neutrons are produced from a large and expensive particle accelerator called a cyclotron. This high-LET (high linear-energy-transfer) radiation is also referred to as “fast neutron therapy”. Neutrons, pions and heavy ions (such as carbon, neon and argon) deposit more energy along their path than x-rays or gamma rays, thus causing more damage to the cells they hit. The cyclotron accelerator produces protons and then a series of powerful magnets bend and aim the beam to strike a beryllium target, where the interaction produces neutrons.
    [Show full text]
  • Protection Against Neutron Radiation up to 30 Million Electron Volts
    PROTECTION AGAINST NEUTRON RADIATION UP TO 30 MILLION ELECTRON VOLTS Handbook 63 U. S. Department of Commerce National Bureau of Standards HANDBOOKS OF THE NATIONAL BUREAU OF STANDARDS The following Handbooks issued by the Bureau are avail¬ able by purchase from the Superintendent of Documents, Government Printing Office, Washington 25, D. C., at the prices indicated: No. Price 28 Screw-Thread Standards for Federal Services 1944-$1.25 28 1950 Supplement to Screw-Thread Standards for Federal Services 1944 .60 28 Screw-Thread Standards for Federal Services 1957, Part I. (Amends in part H28 1944 and in part its 1950 Supplement) . 1.25 30 National Electrical Safety Code. 2.25 37 Testing of Weighing Equipment. 2.50 42 Safe Handling of Radioactive Isotopes.20 43 Installation and Maintenance of Electric Supply and Communication Lines. Safety Rules and Discussion.. 2.25 44 Specifications, Tolerances, and Regulations for Commer¬ cial Weighing and Measuring Devices—2d Edition.... 2.00 45 Testing of Measuring Equipment . 1.50 46 Code for Protection Against Lightning.45 48 Control and Removal of Radioactive Contamination in Laboratories .15 49 Recommendations for Waste Disposal of Phosphorus-32 and Iodine-131 for Medical Users.15 50 X-ray Protection Design.20 51 Radiological Monitoring Methods and Instruments.20 52 Maximum Permissible Amounts of Radioisotopes in the Human Body and Maximum Permissible Concentra¬ tions in Air and Water.25 53 Recommendations for the Disposal of Carbon-14 Wastes .15 54 Protection Against Radiations From Radium, Cobalt-60,
    [Show full text]
  • Thermal Neutron Detection
    Thermal Neutron Detection Louie Cueva December 8, 2015 PHYS 575 1 Neutrons • 1932 – Chadwick discovered the neutron • No charge, No Coulomb force, No Service! • Interaction with detectors • Interactions with nuclei • ~10 min life time (free neutron) • Sources Fig 1. Chadwick (nobelprize.org) • Nuclear Reactors, Spallation (accelerator based), Fusion sources (D-T), Radioactive decay (252Cf, 250Cm, 240Pu) • Applications • Nuclear, material science, imaging, medical physics 2 Neutron Energy Ranges INTERACTIONS < 0.005 eV Cold Diffraction 0.025 eV Thermal 0.02 eV Epithermal Capture Elastic (η,γ)(η,p)(η,α) Scattering 1–10 eV Slow Fission 300 eV ‐ 1 MeV Intermediate (η,f) 1 –20 MeV Fast Inelastic > 20 MeV Ultra Fast Scattering (η,χ) 3 Interaction with Matter Extremely weak electromagnetic interactions Radiation Protection Penetration through matter • Shielding is more complicated Nuclear interactions only, low probability at that Interaction is inversely proportional to energy • It’s about probability, not density • Atypical materials: paraffin, borated materials (concrete, water, polyethylene) Fig 2. Neutron Interaction (explorcuriosity.org) 4 Neutron Cross Section • Cross section is measure of the probability for a reaction between particles • “Barn” has area dimensions (10-28 m2) • Microscopic – probability of reaction between neutron and nucleus • Macroscopic – probability of interaction between neutron and material • Typical reactions Fig 3. neutron reactions (nucleonica.net) 5 Neutron Detection Cross Section vs. Energy • Cross section goes down as energy increases so slow neutrons (thermal) have a vastly different detection scheme than fast neutrons • Moderator material is used to slow neutrons down thereby generally increasing detection efficiency (to an extent…) • Fast Neutron spectroscopy allows for detection to quantify incoming neutrons and deduction of incoming neutron energy.
    [Show full text]
  • Neutron Measurements Around High Energy X-Ray Radiotherapy Machines
    AAPM REPORT NO. 19 NEUTRON MEASUREMENTS AROUND HIGH ENERGY X-RAY RADIOTHERAPY MACHINES Published for the American Association of Physics in Medicine by the American Institute of Physics AAPM REPORT NO. 19 NEUTRON MEASUREMENTS AROUND HIGH ENERGY X-RAY RADIOTHERAPY MACHINES A REPORT OF TASK GROUP 27 RADIATION THERAPY COMMITTEE AMERICAN ASSOCIATION OF PHYSICISTS IN MEDICINE Ravinder Nath, Yale University, Chairman Arthur L. Boyer, M.D. Anderson Hospital Philip D. La Riviere, Varian Associates Richard C. McCall, Stanford Linear Accelerator Center Kenneth W. Price, Yale University July 1986 Published for the American Association of Physicists in Medicine by the American Institute of Physics Further copies of this report may be obtained from Executive Officer American Association of Physicists in Medicine 335 E. 45 Street New York, NY 10017 Library of Congress Catalog Card Number: 86-73193 International Standard Book Number: 0-88318-518-0 International Standard Serial Number: 0271-7344 Copyright © 1987 by the American Association of Physicists in Medicine All rights reserved. No part of this publication may be reproduced, stored in a retrieval system, or transmitted in any form or by any means (electronic, mechanical, photocopying, recording, or otherwise) without the prior written permission of the publisher. Published by the American Institute of Physics, Inc., 335 East 45 Street, New York, New York 10017 Printed in the United States of America Table of Contents I. Introduction 3 II. Measurements Inside the Treatment Room A. General Considerations 4 B. Phosphorus Activation Method 9 C. Moderated Foil Method 13 D. Activation Rem Meter Method 19 III. Measurements Outside the Treatment Room 24 IV.
    [Show full text]
  • Long-Range Neutron Detection
    JNNL-13044 PacificNorthwest National Laboratoy Operated by Battelle for the U.S. Depa@ment of Energy LongRange Neutron Detection A.J. Peurrung D.C. Stromswold R.R. Hansen P.L. Reeder D.S. Barnett November 1999 Prepared for the U.S. Department of Energy under Contract DE-AC06-76M0 1830 DISCLAIMER This report WASprepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereofi nor Battelle Memorial Institute, nor any of their employees, makes any warranty, expressed 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. Reference herein “to any specific commercial product process, or service by trade name, trademark manufacturer, or o.lherwise does not necessarily constitute or imply its endorsemen~ recommendation, or favoring by the United States Government or any agency thereof or BatteHe Memorial - Institute. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. PACIFIC NORTHWEST NATIONAL LABORATORY operated by BAITELLE MEMORIAL IN- ~ forthe UNITED =ATES DEPARTMENT OF ENERGY under ContractDE-AC06-76RL01830 ,, ,, Printed in tbe United States of America Available to DOE and DOE contractors from the OffIce of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; prices available from (615) 576-8401. ,, Available to the public fr,omthe National Technical Information Service, U.S. Department of Commerce,’5285Port Royal Rd., Springfield, VA 22161, ,.
    [Show full text]
  • Table of Contents
    ORAU Team Document Number: ORAUT-TKBS-0006-6 NIOSH Dose Reconstruction Project Effective Date: 10/05/2006 Revision No.: 01 PC-1 Technical Basis Document for the Hanford Site – Controlled Copy No.: ______ Occupational External Dosimetry Page 1 of 80 Subject Expert: Jack Fix Supersedes: Document Owner Approval: Signature on File Date: 01/09/2004 Edward D. Scalsky, TBD Team Leader Revision No.: 00 Approval: Signature on File Date: 01/09/2004 Judson L. Kenoyer, Task 3 Manager Concurrence: Signature on File Date: 01/09/2004 Richard E. Toohey, Project Director Approval: Signature on File Date: 01/09/2004 James W. Neton, OCAS Health Science Administrator TABLE OF CONTENTS Section Page Record of Issue/Revisions ................................................................................................................... 5 Acronyms and Abbreviations ............................................................................................................... 6 6.1 Introduction ................................................................................................................................. 8 6.1.1 Purpose ............................................................................................................................ 9 6.1.2 Scope ............................................................................................................................... 9 6.2 External Dosimetry ...................................................................................................................... 9 6.3 Basis of
    [Show full text]