Radiation Protection Operation for Exempt Personnel Fall 1964 (Gec, Hanford Laboratories)

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I, METHODS OF SAMPLING 1, Principle of Operation 2. Particle Size Range 4. Equipment and use 2) Goetz Aerosol Spectrometer Be Electrostatic Pre c ip it at or s 1. Principle of Operation 2. Particle Size Range C. Thermal Pre c ip it at or s 1. Principle of Operation bo Inertial Collection do Electrostatic Attraction

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2. Commerical Filter Media a, Cellulose Fiber Paper do Membrane Fiber Filters e. Mixed Fiber Paper 3Filter Advantages and Disadvantages b o Pu aerosol monitoring A. Alpha Air Monitoring 2. Alpha Energy Analysis 1. Fixed o r Moving Tape

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C, Tritium or Gas Monitors 1. Ion Chamber Devices I11 AIR SAMPLING AIVD MOFJITORIFIG EVALXIATIOY B. Air Sample Counting b o Alpha energy analysis c. Gamma energy analysis 1. Lung deposition model IV. SAMPUNG ERRORS OR PROBLEMS 1. I kf in it ion 2. Effect of Errors 3 ,, Stack Effluent Monitoring 4, Room Air Samplers B, Calibration of Flow Rate Meters Improper Seating of Filter Media Scrubber Packing and Solution Entrainment

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RADIATION PROTECTION COUSE FOR MEMpT PEBOIONEL 1, Administrative Aspects of Radiation Protection L. A. Carter - .l.- c. tec tion at the different levels in an organization. Mscussion of the application of the various fm8chanismo and techniques available .for use In administration of radiation protection programs L. Ar Carter2, Leuislation and Radiation Protection Trends. ., A review of present State and Federal legisla tion, incliading regulations for licensee6 of ' the AEC. Discussions will cover the general _ types of legislation which have been enacted o r are proposed, and some of the pitfalls which could reault from poorly-written legislation on Mi curs ion of current rad la tion dose units, their origin and bases, and recent developments i n definition and nomenclature. Review of the history of radiation protection, .and the development of' the-concept of ped ssi ble radiation dose, including t h e current bases of permissible dose _ _f o r both intrrnal and external radiation. Calibration of Radiation Instruments * .CeMa ullruh An explanation of calibration methodso Mscussion will cover radiation sources used as standards, methods of establishing standard . emission from sources, use of ictoreen "R" meters, free air ionization chambers, and foil activation procedures The adaptation of laboratory methods t o routine calibration procedures will be covered, This will include consideration of scatter, energy dependence of instruments, source size and geometries, instrument response time and calibration

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Application of Available Dose Rate Monitorinq Instlvments to Field Use Discussion Will include consideration of the various factors involved in field monitoring to field use will be reviewed with special emphasis on practical methods for attaining high quality measurement of radiation dose t o The adaptation of available equipment Internal and External Radiation Dosimetry A discussion of methods and instnunentation available for dose mearunment with particular emphasis on those used atWOO The development of current HAP0 dosimetry systems will be reviewed, including their capabilities and Radiation Record Systems and R0P;rams A discuasion of the bases of the HAP0 system of radiological records,' the different class i - fi cations of records the influence of quality and completeness of records, and t h e methods used t o obtain satisfactory recordso The various uses of radiological records, including their application i n court cases will be reviewed, Radioactive Wastt Management . A review of redioactive waste hsndling at WOO Discussion will cover both waste disposal and long term storage, with major emphasis on the and hydrological factors on ground disposal will be includedo The favorable influence of geologYcal Effects of Radiation on Livin R Tissue. Tdc fundamental theories of radiobiological action a t the cellular level,, primary and secondary blochemica1 reactions in the intact animal, genetic effects, physiological and pathological changes, modification of radiation injury, special problems of internal sources of radiation, and long-range effects such as accelerated aging, alterations in lifespan, and increased incidence .of tumor C o Ma Uruyh 9-30-64 10-12 noon

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A review of past, current, and rUture radiotin ent findings, especially those of interest in the overall operation of WOO Bmironmcntal Contaminatioa Problems and Problems associated with the release of ’lowlevel radioactive effluents to the air and water of the en v irks, monitoring and sampling programs, important enyiroamcntal factors, and evaluation of improvement of evaluations will also be discussed, Current studies directed toward DiscuPSsion will involve the application of current analysis techniques t o measurement of radioactive material i n water, air, soil, end t ional chemical techniques and the newer gamma pulse analysis techniques will be reviewed. The influence of variables and their correction will be emphasized. Since guffieient amnrnts of fissionable materials of groper composition and configuration may become critical, even outside a reactor, a safety problem exists i n the handling, processing and storage of these materials. The basic problem is one of preventing occurrence of an uncontrolled critical it y in an unshielded situation during these operations . The general concepts and properties of neutron multiplying system will be reviewed, as an introduction to the different factors which determine critical conditions, Preventing the occurrence of a critical system by control of these factors Vi11 be discussed thoroughlyo ’ Examples of nuclear safety criteria will be Evaltiation of +he environmental consequences of the accidental release of large quantities of radlmuclides will be discussed, The various parameters bearing on such a release will be described, and the effect of the more important ones on the analysis will be examined,

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A review of available air sampling methods and equipment, with recamendations on their aspects of air sampling, and adequate coverage will be given t o methods of sampling, methods of measurement, and calculation of data. Discussion will include analysis of how and where air sampling can be used effectively,the importance of air sampling i n routine and emergency situations, and the position of air sampling i n an overall radiation protection program. falls in installation and use of air sampling equipment will also be covered. Emphasis will be on the monitoring 16. Radioloffical Bx in e er fn q La G. Faust 11-25-64 8-12 noon Discussion will center on good design practices, and include such topics as floor plans,’ air flows, shielding, instrumentation, and storage and disposal of waste. pressions will be developed for use i n shLelding calculations, and t h e various parameters involved i n evaluation of shielding requirements will be discussedo will be presented, Typical illustrative examples

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LEGISLATION AND RADIATION PROTECTION TRENDS A. Federal Radiation Council B. National Committee on Radiation Protection C. International Commission on Radiation Protection TYPES OF RDXLATIONS OR STANDAFDS FEDERAZ LEGISLATION AND RM;ULATION A. Atomic Energy Ccamnission 2. Title 10 Code of Federal Regulations (Licensees) B. Interstate Commerce Commission (49 CFR 73) STATE LEGISLA!I!ION AND REGULATION A. Transfer of Regulatory Responsibility from the , States Having Completed Agreements with the AECB. C. State of Washington The Past Position of Hanfordr The Impact of Current Trends on Hanford Department of Labor ( 4 1 CFR 50-204) EC t o the Sta ;e

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AlKEKSTRATIVE ASPECTS OF RADIATION PROTECTION AT HAPO Federal Regulations and the AEC Manual Recommendations of t h e NCRP and ICRP 11. ASSIGNMENT OF RESPONSIBILITIES 1. Establish basis of radiation protection program through appropriate Standaxds and Procedures. Individual employee dose measurement and evaluation relative 3. Reports and records of radiation protection experience Control of individual employee exposure Control of sources of radiation Avoidance of accidents o r incidents Accomplishing necessary work with minimum exposure Compliance with established rules and regulations Reporting unusual. conditions t o supervision D. Industrial Medical (evaluation of radiation exposure relative to health and welfare) 111. SPECIFIC AREAS OF INTEREST A. HAPO Policies and Standards

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I). Incidents and Investigations 1. AEC - Class A and B. 3. Source Control and Release

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I. RADIATION DOSE UNITS The l3fo Kinds of "Dose" and Their Relation 1. Free Air Chamber Re cent Changes Dosimetry f o r Personnel Protection 1. Dose Equivalent (RBE Dose) From Exposure Dose Chambers, etc. 11. PERMISSIBLE RADIATION DOSE A. History of Safety Standards 3. Maximum Permissible Doses 4. Radiation Protection Guide Maximum Permissible Body Burdens - Radium and Bone Seekers Maximum Permissible ConcentratIan o r Intake

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Mecoverp of radioactivity Chemical dosimeter, color changes Barium platinocyanide past ille s Unit: one ion pair Free air chamber concept$ Pa. i n 0-5 mm F% at 2 em The knaan roentgen Air wall chambers (Birth of the Standard free air chamber Units: rep, rem Ad hoc committee on quantities and Handbook 84; fluence, Lema, dose and exposure , dose equivalent, one csu per cc of air same ionization as 1 g of

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Discovery of radioactivity Roentgen Society (British) began t o collect in format ig on inJwious effects Safe if film not fogged i n seven Roentgen Society issued recommendations British X-ray and Radium Protection Committee formed; first report American Roentgen Ray Society ad0pte.d rules on radiation protection 0.01 ergthema dose p e r month German Committee on X-ray and Radiation First International Congress of Radiology; ICRU formed 0.1 erythema dose per year 1/300 erythema dose per day Dutch Board of Health 1/70 &ythems dose per day 0.00028 erythema dose per day 0.005 erythema dose per day League of Rations, about 0.25 R/day 0,001 erythema dose per month US. Adv. Comm, 0,l R/day t o allow f o r greater penetration of higher U,S. Adv. Comm. chezlged t o NCRP Tri-Partite conference at Chalk River 0.3 R/week measured in sir Federal Radiation Council formed Radiation Protection Guides Safe i f less than Maxi - permissible dose Approximate Erythema Doses

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CALIBFATION OF RADIATlOM IEJSTRUMEIJTS I. Radiation Sources used f o r Calibrations 11. Primary Calibration of Radiation Sources C. Free A i r Ion Chamber A. Dose Rate Instruments B o Detection Type Instruments Do Emergency Monitoring Equipment IV,Visit to Calibration facility to include a first hand look atall calibration equipment and methods. V. General question and discussion period

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APPWCATION OF AVAILABLE DOSE RATE MONITORING INSTRUMENTS TO FIELD USE C. Instrument response characteristics 11. How does m e determine correction factors ? 111, Correct methods of Interpretations for specific monitoring situations IV. Improvements t o be made B o Improved calibration methods V. General question and discussion period

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STATIONARY WHOLE BODY COUNTER The Whole Body Counter is used both in research programs and i n routine evaluation of whole body content of a wide variety of gamma-ray emitting evaluation in the thyroid, and quantitative measurement of pluto nia deposited in superficial wounds. sodium 24 Inthe blood, which I s very useful In estimating personnel dOSC i n went of a critical it y Incident, With ouitable cryotalo the unit i s also used for iodine 131 The unit is a160 capable of accurate measurement of This is a cut-away drawing of the stationary Whole Body Counter. The facilities house several locker rooms, a reception roan, a counting roam, M analysis room and an equipment rep a lr shop. is their on room i n which the measurement takes place. music i s played over an intercom systun. Installed for viewlng the patient remotely. special value when children are being cxsmlned, The heart of the Whole Body Counter The roan is made of The counting room is air conditioned and Also,a television camera was This latter feature hns proven Of

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nuclides, the patient (shown in slide) sits in a reclining chair and a 9 inch by 4 lnch sodium iodide crystal is placed in a geometry such that the pcrtlent's bow forms an arc around the crystal. nanocurie (fora lo-minute counting time) for mort radionuclides. assembly may be placed on a track in such a geometry that the crystal can remotely The detection limit of the crystal is about one scan a patient reclining on a litter. This counting geometry i s used t o determine the location of an Isotope in the body.

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WHOLE BODY COulpTER LABORATORY CONSOLE The Whole Body Counter Laboratory Console is designed for maximum reed-out capability. !he heart of t h e system Is an RIDL Model 43-12, 400 channel pulse height analyzer, Use of either tv o channel o r four channel mixer cMpliflers allows simultaneous uue of one, two, three or four detectors inthe iron ro anD Examination measurements are displayed on the analyzer scope i n the form of total counts as 8 function of gama-ray energy. permits the accumulated data t o be printed out on paper tape in t h e form of total counts per ch&nnelD allows t h e data t o be read out l a binary coded decimal tom for IBM computer A manual address and punched paper tape system stripping or storage of data t o be replayed i n t o the anslyzervs memory Core at a later time. A digital magnetic tape recorder may be used for spectrum Also, an X-Y plotter permits automatic graphing of data for

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PLUTONIUM WOUND COUNTER A wound counter i s available for detecting and locating plutonium in cuts, wounds, puncturer and abrasions either on or,i nthe skin toR depth of a few millimeters, of the cry r tal permlts optimum counting of the 17 kev X-rsy emitted *an a Small aperture over the suspected injury until the maximum counting rate i s physicist and the physician i n defining sections, of ti6suc t h a t should be uccieed i n order t o remove the isotope frm the body, Th insensitive counter consists of a 1-3/4 inch The detection limit of the cryrtal l r about 0.1 nanocurie for The wound is located by moving a shield containing Thir detector hacr proved t o be an invaluable tool to both the health

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This elide shows a subject being examined for the prerence of radioiodine in t h e thyroid. RaI crystal and photanultiplier tube mounted on the boom of a movable dolly. Thie arrangement allaws the detector t o be easily adjusted for any 8Ub jt Ct 80 that the cry at al sxlr will be perpendicular tothe subject's neck, just thin pocition l a 20 pc fora 30-zainute counting time. The detector system used i 8 a 3 inch by 3 inch The detection limit for 1131 with the detector in

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The detection capabilities of' the Whole Body Counter that 8re ahin this slide m e based upon a lOJninute counting time with the 6UbJeCt in the chair geunetry poeition, m s y be lowered by longer counting time. and different gccoretrier, nuclideo are typical ones frequently measured in Hanford employee8 with the exception of 1131 and PU239. mployees involved in on-plant radiation exposure Sncident8 The detection levels listed for 1131 are based OD 30-minute counting the6 using a 3 inch by 3 inch NaI crystal thyroid counter or a 9-3/8 inch by 4 inch NaI crystal In special situations, the at tec tion levels These latter two nuclide8 have been meamred i n Other gamma-emitting nuclides are less frequently seen, but t h e i r detection levels are canparable t o those listed,

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MOBILE WHOLE BODY COUNTER EXTERIOR The Mobile …