DOCSLIB.ORG

Good Practices for Occupational Radiological Protection in Plutonium

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Good Practices for Occupational Radiological Protection in Plutonium Not Measurement Sensitive DOE- STD-1128-2013 April 2013 DOE STANDARD GOOD PRACTICES FOR OCCUPATIONAL RADIOLOGICAL PROTECTION IN PLUTONIUM FACILITIES U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1128-2013 This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ ii DOE-STD-1128-2013 Foreword This Technical Standard does not contain any new requirements. Its purpose is to provide information on good practices, update existing reference material, and discuss practical lessons learned relevant to the safe handling of plutonium. U.S. Department of Energy (DOE) health physicists may adapt the recommendations in this Technical Standard to similar situations throughout the DOE complex. The Standard provides information to assist plutonium facilities in complying with Title 10 of the Code of Federal Regulations (CFR), Part 835, Occupational Radiation Protection. The Standard also supplements the DOE 10 CFR 835 Implementation Guide, DOE Orders, and DOE standard, DOE-STD-1098-2008, Radiological Control, (RCS) and has as its sole purpose the protection of workers and the public from the radiological hazards that are inherent in plutonium storage and handling. This Standard uses the word “shall” to identify a required practice or the minimum acceptable level of performance. The word “should” is used to identify good practices (preferred practices) recommended by this Standard. The word “may” is used to identify permitted practice (neither a requirement nor a recommendation). This Standard includes provisions in the 2007 amendment to 10 CFR 835. This amendment updated the dosimetric terms and models for assessing radiation doses, both internal and external. Of particular interest for this Standard, the biological transportability of material is now classified in terms of absorption types; F (fast), M (medium) and S (slow). Previously this was classified in terms of material class; D (days), W (weeks) and Y (years). Throughout this Standard, discussions of previous studies describing the biological transportation of material in the body will continue to use D, W and Y, as appropriate. Discussions of other requirements which have not amended their dosimetric terms and models continue to use the older terminology. This Standard does not include every requirement applicable to every plutonium facility. Individuals responsible for implementing Radiation Protection Programs at plutonium facilities need to be knowledgeable of which requirements (contractual or regulatory) are applicable to their facility. Copies of electronic files of this Technical Standard may be obtained from either the DOE Radiation Safety Home Page Internet site (http://www.hss.energy.gov/HealthSafety/WSHP/radiation/ts.html) or the DOE Technical Standards Program Internet site (http://www.hss.doe.gov/nuclearsafety/techstds/standard.html). iii This page intentionally left blank. iv U.S. DEPARTMENT OF ENERGY GOOD PRACTICES FOR OCCUPATIONAL RADIOLOGICAL PROTECTION IN PLUTONIUM FACILITIES Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of Energy DOE-STD-1128-2013 TABLE OF CONTENTS 1.0 INTRODUCTION…………………………………………………………………... 1-1 1.1 PURPOSE AND APPLICABILITY…………………………………………..1-1 1.2 DEFINITIONS………………………………………………………………...1-1 1.3 ACRONYMS………………………………………………………………... 1-2 1.4 DISCUSSION……………………………………………………………….. 1-3 2.0 MANUFACTURE, PROPERTIES, AND HAZARDS……………………………... 2-1 2.1 MANUFACTURE OF PLUTONIUM……………………………………….. 2-1 2.2 NUCLEAR PROPERTIES…………………………………………………... 2-3 2.3 PHYSICAL AND CHEMICAL PROPERTIES……………………………… 2-7 2.4 RADIOLOGICAL EFFECTS ON HUMANS………………………………... 2-14 2.5 RADIATION EFFECTS ON MATERIALS…………………………………. 2-18 2.6 OCCUPATIONAL HAZARDS………………………………………………. 2-22 2.7 STORAGE AND CONTAINMENT…………………………………………. 2-28 3.0 RADIATION PROTECTION………………………………………………………..3-1 3.1 REGULATION AND STANDARDS………………………………………... 3-1 3.2 RADIATION PROTECTION PROGRAMS…………………………………. 3-2 3.3 RADIOLOGICAL CONTROL ORGANIZATIONS……………………….... 3-11 3.4 STAFFING AND STAFF QUALIFICATIONS………………………………3-12 3.5 INSTRUMENTATION CONSIDERATIONS……………………………….. 3-13 3.6 RADIATION SAFETY TRAINING…………………………………………. 3-22 3.7 RADIOLOGICAL RECORDS……………………………………………….. 3-25 3.8 ALARA AND OPTIMIZATION……………………………………………...3-27 3.9 CONDUCT OF OPERATIONS………………………………………………. 3-28 4.0 CONTAMINATION CONTROL……………………………………………………4-1 4.1 AIRBORNE CONTAMINATION CONTROL…………………………….. 4-1 4.2 SURFACE CONTAMINATION CONTROL………………………………... 4-6 4.3 PERSONNEL CONTAMINATION CONTROL…………………………….. 4-17 4.4 PERSONNEL DECONTAMINATION……………………………………… 4-22 5.0 INTERNAL DOSIMETRY…………………………………………………………. 5-1 5.1 INTERNAL DOSE EVALUATION PROGRAM……………………………. 5-1 5.2 CHARACTERIZATION OF INTERNAL HAZARDS……………………… 5-9 5.3 SCOPE OF BIOASSAY PROGRAM…………………………………………5-10 5.4 ESTABLISHING BIOASSAY FREQUENCY………………………………. 5-15 5.5 ADMINISTRATION OF A BIOASSAY PROGRAM………………………. 5-17 5.6 MODELING THE BEHAVIOR OF PLUTONIUM IN THE BODY………... 5-20 5.7 INTERPRETATION OF BIOASSAY RESULTS…………………………… 5-24 5.8 DOSE ASSESSMENT……………………………………………………….. 5-28 5.9 INDICATOR AND ACTION LEVELS……………………………………… 5-33 5.10 RESPONSE TO SUSPECTED INTAKES…………………………………… 5-36 ii DOE-STD-1128-2013 CONTENTS – (Continued) 6.0 EXTERNAL DOSE CONTROL……………………………………………………. 6-1 6.1 DOSE LIMITS………………………………………………………………... 6-1 6.2 RADIATIONS IN PLUTONIUM FACILITIES……………………………... 6-5 6.3 RADIATION DETECTION AND EVALUATION………………………….. 6-20 6.4 EXTERNAL DOSE REDUCTION…………………………………………... 6-32 7.0 NUCLEAR CRITICALITY SAFETY………………………………………………. 7-1 7.1 REGULATIONS AND STANDARDS………………………………………. 7-2 7.2 CRITICALITY CONTROL FACTORS………………………………………7-2 7.3 CRITICALITY ACCIDENT EXPERIENCE………………………………… 7-6 7.4 CRITICALITY ALARMS AND NUCLEAR ACCIDENT DOSIMETRY….. 7-8 7.5 RESPONSIBILITIES OF HEALTH PHYSICS STAFF……………………... 7-12 7.6 DEPARTMENT OF ENERGY PLUTONIUM VULNERABILITY ANALYSIS STUDY…………………………………………………………. 7-14 8.0 WASTE MANAGEMENT………………………………………………………….. 8-1 8.1 POTENTIALLY CONTAMINATED WASTES…………………………….. 8-1 8.2 AIRBORNE WASTE…………………………………………………………. 8-5 8.3 SOLID WASTE………………………………………………………………. 8-8 8.4 LIQUID WASTE …………………………………………………………….. 8-14 9.0 EMERGENCY MANAGEMENT…………………………………………………...9-1 9.1 EMERGENCY MANAGEMENT IN DOE…………………………………... 9-1 9.2 SPECIFIC GUIDANCE ON EMERGENCY MANAGEMENT FOR PLUTONIUM FACILITIES………………………………………………….. 9-3 10.0 DECONTAMINATION AND DECOMMISSIONING……………………………..10-1 10.1 REGULATIONS AND STANDARDS………………………………………. 10-1 10.2 DESIGN FEATURES…………………………………………………………10-6 10.3 DECONTAMINATION AND DECOMMISSIONING PROGRAM REQUIREMENTS……………………………………………………………. 10-9 10.4 DECONTAMINATION AND DECOMMISSIONING TECHNIQUES…….. 10-9 10.5 DECONTAMINATION AND DECOMMISSIONING EXPERIENCE…….. 10-10 11.0 REFERENCES………………………………………………………………………. 11-1 APPENDIX: GLOSSARY…………………………………………………………….A-1 iii DOE-STD-1128-2013 FIGURES 2.1 Principal Mode of Plutonium Production by Neutron Irradiation of Uranium……….. 2-2 2.2 Atom Ratio of 241Am to 241Pu (t=0) Produced by the Beta Decay of 241Pu as a Function of Time Since Chemical Separation………………………………………….2-7 2.3 Neutron Energy Spectra of Plutonium-Beryllium and Plutonium-Boron Neutron Sources Compared with a Fission Source…………………………………….2-8 2.4 Hazards in Low-Exposure Plutonium Handling………………………………………. 2-24 6.1 Absorbed Surface Dose Rate from Plutonium Dioxide as Measured with an Extrapolation Chamber………………………………………………………...6-6 6.2 Energy Dependence of Various TLD-Albedo Dosimeters……………………………..6-23 6.3 Response of Electrochemically Etched CR-39 Used in Nuclear Track Dosimeters as a Function of Neutron Energy ………………………………………… 6-23 6.4 Fixed Nuclear Accident Dosimeter Used at Hanford to Help Assess Doses from Criticality Accidents……………………………………………………………... 6-27 6.5 Neutron Energy Spectra as Measured by the Multisphere Spectrometer at 50 cm from Plutonium Metal, PuO2, and PuF4 Sources……………………………….. 6-31 6.6 Reduction in Photon Dose Rate with Various Shielding Materials at a Distance of 3 cm from a 100-gram Disk of Plutonium Oxide………………………… 6-36 6.7 Reduction in Neutron Dose Rate for Various Slab Shields for Plutonium Tetrafluoride Sources…………………………………………………...6-37 6.8 Reduction in Neutron Dose Rate for Various Slab Shields for Plutonium Oxide Sources………………………………………………………….. 6-38 iv DOE-STD-1128-2013 TABLES 2.1 Isotopic Composition of Three Grades of Plutonium: Heat Source, Weapons, and Reactor…………………………………………………………………………….. 2-2 2.2 Uses and Availabilities of Plutonium Isotopes………………………………………... 2-3 2.3 Radioactive Decay Properties of Selected Isotopes and Decay Products, Excluding Spontaneous Fission………………………………………………………...2-5 2.4 Specific Activity Decay Heats of Selected Isotopes…………………………………... 2-6 2.5 Allotropic Forms of Plutonium Metal……………………………………………….. 2-9 2.6 Solubilities and Properties of Selected Compounds…………………………………… 2-12 2.7 Common Biokinetic Models for Plutonium and Americium………………………….. 2-18 2.8 Potential Hazards or Damage to Materials from Exposure to Radiation……………… 2-20 2.9 Hazards of Chemicals Used in Processing Plutonium………………………………… 2-25 2.10 Storage Recommendations for Plutonium Metal and Dioxide…………………………2-30 2 4.1 Surface Contamination Values, dpm/100 cm ……………………………………………………………………… 4-3 5.1 Urine Bioassay Goals for 239Pu………………………………………………………… 5-4 5.2 Fecal Bioassay Goals for 239Pu………………………………………………………… 5-5 5.3 In Vivo Lung Measurement Bioassay Goals for 241Am as an Indicator of Aged Weapons Grade Plutonium…………………………………………………………….
Load more

Recommended publications
  • Export Control Handbook for Chemicals
    Export Control Handbook for Chemicals -Dual-use control list -Common Military List -Explosives precursors -Syria restrictive list -Psychotropics and narcotics precursors ARNES-NOVAU, X 2019 EUR 29879 This publication is a Technical report by the Joint Research Centre (JRC), the European Commission’s science and knowledge service. It aims to provide evidence-based scientific support to the European policymaking process. The scientific output expressed does not imply a policy position of the European Commission. Neither the European Commission nor any person acting on behalf of the Commission is responsible for the use that might be made of this publication. Contact information Xavier Arnés-Novau Joint Research Centre, Via Enrico Fermi 2749, 21027 Ispra (VA), Italy [email protected] Tel.: +39 0332-785421 Filippo Sevini Joint Research Centre, Via Enrico Fermi 2749, 21027 Ispra (VA), Italy [email protected] Tel.: +39 0332-786793 EU Science Hub https://ec.europa.eu/jrc JRC 117839 EUR 29879 Print ISBN 978-92-76-11971-5 ISSN 1018-5593 doi:10.2760/844026 PDF ISBN 978-92-76-11970-8 ISSN 1831-9424 doi:10.2760/339232 Luxembourg: Publications Office of the European Union, 2019 © European Atomic Energy Community, 2019 The reuse policy of the European Commission is implemented by Commission Decision 2011/833/EU of 12 December 2011 on the reuse of Commission documents (OJ L 330, 14.12.2011, p. 39). Reuse is authorised, provided the source of the document is acknowledged and its original meaning or message is not distorted. The European Commission shall not be liable for any consequence stemming from the reuse.
    [Show full text]
  • 00419717.Pdf
    APPROVED FOR PUBLIC RELEASE APPROVED FOR PUBLIC RELEASE APPROVED FOR PUBLIC RELEASE ~ ,—- UNWMFIED — PUBUCLYREI-EMABLF . ,$5 ~ .~16f3 This Document Consists of 18 Pages /“ @ LQS ALAMOS SCIENTIFIC LABORATORY Contribution from Chemistry-MetallurgyDivision E. R. Jette, Division Leader J. F, Lemons, Group Leader Plutonium~‘=Hexaf uor e: Preparation and Properties w A. E. Flor November 9, 1950 — ‘1” Chemistry-Tranwrs.nicElements “-+ - ,- —. 1 Y– -t APPROVED FOR PUBLIC RELEASE — APPROVED FOR PUBLIC RELEASE LA-I.M8 UNCLASSIFIED Los tiSDIOS 1-20 STANDARD DISTRIBUTION Argonne,I?ationslLaboratory 21-30 Atomic Energy Commission, Washington 31-32 Brookhaven National Laboratory 33-36 Carbide and Carbon Cheticals Division (K-25 Plant) 37-38 Carbide and Carbon Chemicsl.sDivision (Y-12 Plant) General.Electric Company, Richland Z-45 Hanford Operations Office 46 Iowa State College 47 Kellex Corporation 4.$ Knolls Atomic Power Laboratory g-;; Mound Laboratory Navel Radiological Defense Laboratory 56- NEPA Project 57 New York Operations Office 58-59 Oak Ridge National Laboratory 60-65 Patent Branch, Washington 66 Technical Information Division, ORE 6741 UCLA Medical Research Laboratory (Warren) University of California Radiatio nLaboratory %85 University of Rochester 86-87 2 APPROVED FOR PUBLIC RELEASE — APPROVED FOR PUBLIC RELEASE Introduction It is the purpose of this paper to present the results of experi- mental investigations on the chemistry of plutonium hernfluoride con- ducted at this laboratory subsequent to the preparation of report LAMS 1118(1). A more satisfactory apparatus for the preparation is des- cribed. More reliable values for the vapor pressure have been obtained and the related physical constants have been calculated. The rate of decomposition of the compound as a result of the associated alpha radiation has been determined and a preliminary observation on the thermal stability is reported.
    [Show full text]
  • Plutonium an Overview
    Plutonium An overview PDF generated using the open source mwlib toolkit. See http://code.pediapress.com/ for more information. PDF generated at: Thu, 09 Jun 2011 13:52:20 UTC Contents Articles Overview 1 Plutonium 1 Allotropes 23 Allotropes of plutonium 23 Isotopes 25 Isotopes of plutonium 25 Compounds and mixtures 34 Plutonium borides 34 Plutonium carbide 35 Plutonium hexafluoride 36 Plutonium hydride 38 Plutonium(III) chloride 39 Plutonium(III) fluoride 40 Plutonium(IV) fluoride 42 Plutonium(IV) oxide 43 Plutonium-gallium alloy 45 MOX fuel 48 Environment 52 Plutonium in the environment 52 References Article Sources and Contributors 61 Image Sources, Licenses and Contributors 62 Article Licenses License 63 1 Overview Plutonium Plutonium Appearance silvery white General properties Name, symbol, number plutonium, Pu, 94 Pronunciation /pluːˈtoʊniəm/ ploo-toe-nee-əm Element category actinide Group, period, block n/a, 7, f −1 Standard atomic weight (244) g·mol Electron configuration [Rn] 5f6 7s2 Electrons per shell 2, 8, 18, 32, 24, 8, 2 (Image) Physical properties Phase solid Density (near r.t.) 19.816 g·cm−3 Liquid density at m.p. 16.63 g·cm−3 Melting point 912.5 K,639.4 °C,1182.9 °F Boiling point 3505 K,3228 °C,5842 °F Heat of fusion 2.82 kJ·mol−1 Heat of vaporization 333.5 kJ·mol−1 Specific heat capacity (25 °C) 35.5 J·mol−1·K−1 Vapor pressure Plutonium 2 P/Pa 1 10 100 1 k 10 k 100 k at T/K 1756 1953 2198 2511 2926 3499 Atomic properties Oxidation states 7, 6, 5, 4, 3 (amphoteric oxide) Electronegativity 1.28 (Pauling scale) Ionization
    [Show full text]
  • United States Patent Office 2,830,873
    2,830,873 United States Patent Office Patented Apr. 15, 1958 2 active, so that any recovery process must be capable of being carried out by remote control. Second, plutonium 2,830,873 and uranium are members of the actinide rare earth FLUORDE voLATILITY PROCESS FOR THE family and, although they do not have identical charac RECOVERY OF URANUM 5 teristics, the chemical characteristics are sufficiently close Joseph J. Katz and Herbert H. Hyman, Chicago, and that it does increase the difficulty of separation of these Erving. Sheft, Oak Park, I., assignors to the United two elements by chemical methods. States of America as represented by the United States An ideal separation process for the recovery of ura Atomic Energy Commission nium from neutron-irradiated uranium would include the No Drawing. Application May 10, 1956 O following characteristics. The process should be one capable of continuous operation. The process must be Serial No. 584,153 one which can be operated by remote control because of 25 Claims. (CI. 23-145) the radiation hazards involved. Furthermore, it is desir able that the non-radioactive uranium be separated in an The present invention is concerned with the separation 15 early step of the process from the radioactive fission and recovery of uranium from contaminants by a halo products, so that the further processing of uranium may genation and volatilization method. The invention is par be carried on without the shielding required for process ticularly concerned with the recovery of uranium from . ing radioactive materials. The efficiency of the separa contaminants arising from the neutron irradiation of ura 20 tion of the uranium from the plutonium and fission prod nium.
    [Show full text]