Introduction Ionizing Radiation Types And Sources Of .

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IntroductionIonizing RadiationChapter 1F.A. Attix, Introduction to RadiologicalPhysics and Radiation DosimetryIonizing radiation By general definition ionizing radiation ischaracterized by its ability to excite andionize atoms of matter Lowest atomic ionization energy is eV,with very little penetration Energies relevant to radiological physicsand radiation therapy are in keV – MeVrangeTypes and sources of ionizingradiation Fast electrons (positrons) emitted from nuclei (brays) or in charged-particle collisions (d-rays).Other sources: Van de Graaf generators, linacs,betatrons, and microtrons Heavy charged particles emitted by someradioactive nuclei (a-particles), cyclotrons, heavyparticle linacs (protons, deuterons, ions of heavierelements, etc.) Neutrons produced by nuclear reactions (cannot beaccelerated electrostatically) Radiological physics studies ionizingradiation and its interaction with matter Began with discovery of x-rays,radioactivity and radium in 1890s Special interest is in the energy absorbedin matter Radiation dosimetry deals withquantitative determination of the energyabsorbed in matterTypes and sources of ionizingradiation g-rays: electromagnetic radiation (photons) emittedfrom a nucleus or in annihilation reaction– Practical energy range from 2.6 keV (Ka from electron capturein 3718Ar) to 6.1 and 7.1 MeV (g-rays from 167N) x-rays: electromagnetic radiation (photons) emitted bycharged particles (characteristic or bremsstrahlungprocesses). Energies:–––––0.1-20 kV20-120 kV120-300 kV300 kV-1 MV1 MV and up“soft” x-raysdiagnostic rangeorthovoltage x-raysintermediate energy x-raysmegavoltage x-raysTypes of interaction ICRU (The International Commission on RadiationUnits and Measurements; established in 1925)terminology Directly ionizing radiation: by charged particles,delivering their energy to the matter directly throughmultiple Coulomb interactions along the track Indirectly ionizing radiation: by photons (x-rays or grays) and neutrons, which transfer their energy tocharged particles (two-step process)1

Description of ionizingradiation fields To describe radiation field at a point P need todefine non-zero volume around it Can use stochastic or non-stochastic physicalquantitiesStochastic quantities For a “constant” radiation field a number of x-raysobserved at point P per unit area and time intervalfollows Poisson distribution For large number of events it may be approximatedby normal (Gaussian) distribution, characterized bystandard deviation s (or corresponding percentagestandard deviation S) for a single measurementStochastic quantities Values occur randomly, cannot be predicted Radiation is random in nature, associated physicalquantities are described by probability distributions Defined for finite domains (non-zero volumes) The expectation value of a stochastic quantity (e.g.number of x-rays detected per measurement) is themean of its measured value for infinite number ofmeasurementsN Ne for n Stochastic quantities Normal (Gaussian) distribution is described byprobability density function P(x) Mean N determines position of the maximum, standarddeviation s defines the width of the distributionP( N ) s Ne NS e N N 2s 2 / 2s 2100s100 100 NeNeNStochastic quantities For a given number of measurements n standarddeviation is defined assNeN nnn100s 100100S NenN enNs 1 N will have a 68.3% chance of lying within interval s of Ne, 95.5% to be within 2s , and 99.7% to be withininterval 3s . No experiment-related fluctuationsStochastic quantities In practice one always uses a detector. An estimatedprecision (proximity to Ne) of any single randommeasurement Ni 1 s Ni N n 1 i 1n21/ 2N N i n Determined from the data set of n such measurements2

Stochastic quantities An estimate of the precision (proximity to Ne) of themean value N measured with a detector n timess snn 1 Ni N 2 s nn 1i 1 Stochastic quantities: Example A g-ray detector having 100% counting efficiency is positionedin a constant field, making 10 measurements of equal duration,Dt 100s (exactly). The average number of rays detected(“counts”) per measurement is 1.00x105. What is the mean valueof the count rate C, including a statement of its precision (i.e.,standard deviation)?1/ 2C N 1.00 105 1.00 103 c/sDt100C1.00 103 1 c/sn103C 1.00 10 1 c/ss C Ne is as correct as your experimental setup Here the standard deviation is due entirely to the stochastic natureof the field, since detector is 100% efficientNon-stochastic quantities For given conditions the value of non-stochasticquantity can, in principle, be calculated In general, it is a “point function” defined forinfinitesimal volumes– It is a continuous and differentiable function of space andtime; with defined spatial gradient and time rate of change Its value is equal to, or based upon, the expectationvalue of a related stochastic quantity, if one exists– In general does not need to be related to stochasticquantities, they are related in description of ionizingradiationNon-stochastic quantities:Fluence A number of rays crossing an infinitesimalarea surrounding point P, define fluence as dN eda Units of m-2 or cm-2Description of radiation fieldsby non-stochastic quantities FluenceFlux Density (or Fluence Rate)Energy FluenceEnergy Flux Density (or Energy FluenceRate)Non-stochastic quantities:Flux density (Fluence rate) An increment in fluence over an infinitesimally smalltime interval d d dN e dt dt da Units of m-2 s-1 or cm-2 s-1 Fluence can be found through integration:t1 t0 , t1 t dtt03

Non-stochastic quantities:Energy fluence For an expectation value R of the energy carried by allthe Ne rays crossing an infinitesimal area surroundingpoint P, define energy fluence as dRda Units of J m-2 or erg cm-2 If all rays have energy ER EN eDifferential distributions More complete description of radiation fieldis often needed Generally, flux density, fluence, energy fluxdensity, or energy fluence depend on allvariables: , b, or E Simpler, more useful differentialdistributions are those which are functionsof only one of the variables E Differential distributions byenergy and angle of incidence Differential flux density as afunction of energy and angles ofincidence: distribution , b , E If a quantity is a function of energy only, suchdistribution is called the energy spectrum (e.g. E ) Typical units are m-2 s-1keV-1 or cm-2 s-1keV-1 Integration over angular variables gives flux densityspectrum Typical units are m-2 s-1sr-1keV-1 Integration over all variablesgives the flux density: E 0 b 0 E 0(x,y,z) (r, ,b)Differential distributions:Energy spectrum example E E 2 , b , E sin d db b 0 02 Emax , b , E sin d dbdEDifferential distributions:Energy spectra A “flat” distributionof photon flux density Energy flux densityspectrum is found by E E E Typically units for Eare joule or erg, so that[ ’] Jm-2s-1keV-1 Similarly, may define energy flux density E Example: Problem 1.8An x-ray field at a point P contains 7.5x108photons/(m2-sec-keV), uniformlydistributed from 10 to 100 keV.a) What is the photon flux density at P?b) What would be the photon fluence in one hour?c) What is the corresponding energy fluence, inJ/m2 and erg/cm2?4

Example: Problem 1.8Differential distributions:Angular distributionsEnergy spectrum of a flux density (E ) 7.5x108 photons/m2-sec-keVa) Photon flux density E Emax Emin 7.5 108 90 6.75 1010 photons/m2sb) The photon fluence in one hour t 1 hour Dt 6.75 1010 3600 2.43 1014 photons/m2c) The corresponding energy fluence, in J/m2 and erg/cm2 Dt E 100 E EdE Dt E 103600 7.5 108 E2210010 11002 102 1.336 1016 keV/m 2 21.336 1016 1.602 10 16 2.14 J/m 2 2.14 103 erg/cm com/cws/article/cern/28653 Full differentialdistribution integratedover energy leavesonly angulardependence Often the field issymmetrical withrespect to a certaindirection, then onlydependence on polarangle or azimuthalangle bAzimuthal symmetry: a) accelerator beam after primary collimator;b) brachytherapy surface applicatorSummary Types and sources of ionizing radiation– g-rays, x-rays, fast electrons, heavy chargedparticles, neutrons Description of ionizing radiation fields– Due random nature of radiation: expectationvalues and standard deviations– Non-stochastic quantities: fluence, flux density,energy fluence, energy flux density, differentialdistributionsIntroduction Need to describe interactions of ionizingradiation with matter Special interest is in the energy absorbed inmatter, absorbed dose – delivered bydirectly ionizing radiation Two-step process for indirectly ionizingradiation involves kerma and absorbed doseQuantities for Describing theInteraction of IonizingRadiation with MatterChapter 2F.A. Attix, Introduction to RadiologicalPhysics and Radiation DosimetryDefinitions Most of the definitions are by ICRU– ICRU Report 33, Radiation quantities and units, 1980– Revised several times (the latest: ICRU Report 85Fundamental quantities and units for ionizing radiation, 2011) Energy transferred by indirectly ionizing radiation leadsto the definition of kerma Energy imparted by ionizing radiation leads to thedefinition of absorbed dose Energy carried by neutrinos is ignored5

Energy transferred tr - energy transferred in a volume V tocharged particles by indirectly ionizingradiation (photons and neutrons) Radiant energy R – the energy of particlesemitted, transferred, or received, excludingrest mass energy Q - energy delivered from rest mass in V(positive if m E, negative for E m)Kerma Kerma K is the energy transferred to chargedparticles per unit massd tr e d trK dmdm Includes radiative losses by charged particles(bremsstrahlung or in-flight annihilation ofpositron) Excludes energy passed from one chargedparticle to another Units: 1 Gy 1 J/kg 102 rad 104 erg/gEnergy-transfer coefficient Linear energy-transfer coefficient tr ,units of m-1 or cm-1 tr Mass energy-transfer coefficient , E ,Zunits of m2/kg or cm2/g Set of numerical values, tabulated for arange of photon energies, Appendix D.3Energy transferred The energy transferred in a volume V tr Rin u Rout unonr Quncharged R does not include radiative losses ofkinetic energy by charged particles(bremsstrahlung or in-flight annihilation) Energy transferred is only the kineticenergy received by charged particlesnonrout uRelation of kerma to energyfluence for photons For mono-energetic photon of energy E andmedium of atomic number Z, relation isthrough the mass energy-transfer coefficient: K tr E ,Z For a spectrum of energy fluence E E E maxK E 0 E tr dE E ,ZRelation of kerma to fluencefor neutrons Neutron field is usually described in termsof fluence rather than energy fluence Kerma factor is tabulated instead of kerma(units are rad cm2/neutron, Appendix F) Fn E ,Z tr E ,Z E For mono-energetic neutronsK Fn E ,Z6

Components of KermaCollision Kerma Energy received by charged particles may be spentin two ways Subtracting radiant energy emitted bycharged particles Rur from energy transferredresults in net energy transferred locally trnet tr Rur – Collision interactions – local dissipation of energy,ionization and excitation along electron track– Radiative interactions, such as bremsstrahlung orpositron annihilation, carry energy away from the track Kerma may be subdivided in two components,collision and radiative:K Kc K r When kerma is due to neutrons, resulting chargedparticles are much heavier, K KcMass energy-absorptioncoefficient Since collision kerma represents energydeposited (absorbed) locally, introducemass energy-absorption coefficient. Formono-energetic photon beam Rin u Rout unonr Rur Q Now collision kerma can be definedd netK c trdmMass energy-absorptioncoefficient For low Z materials and low energyradiative losses are small, therefore valuesof tr and en are close K c en E ,Z Depends on materials present along particletrack before reaching point PKerma rate Kerma rate at point P and time tdK d d tr K dt dt dm Units of J/(kg s), erg/(g s), or rad/s Knowing kerma rate, kermat1K t0 , t1 K t dtt0Absorbed dose Energy imparted by ionizing radiation tomatter of mass m in volume V Rin u Rout u Rin c Rout c Qdue to unchargeddue to charged Absorbed dose is defined asd D dm Units: 1 Gy 1 J/kg 102 rad 104 erg/g7

Example 1 Rin u hv1 Rout u Rout unonr hv2 Rin c 0, Q 0 Rout c hv3 T Absorbed dose2 D represents the energy per unit mass whichremains in the matter at P to produce anyeffects attributable to radiation The most important quantity in radiologicalphysics Absorbed dose rate: dD d d D dt dt dm 1Rur hv31 Rin u Rout u Rin c Rout c QEnergy imparted tr Rin u Rout unonr QEnergy transferred trnet Rin u Rout unonr Rur QNet energytransferredExample 2Example 1 Rin u hv1 Rout u Rout unonr hv2 Rin c 0, Q 0 Rout c hv3 T 212Positron has no excesskinetic energy to transferto photons afterannihilation312R hv3ru112 hv1 hv2 hv3 T 0 tr hv1 hv2 0 T1Example 3T332123 Positron transfers excesskinetic energy T3 tophotons after annihilation. It generates radiativeloss from charged-particlekinetic energyn Affects and tr bysubtraction of T3 Rin u Rin c Rout c 0 Rout u 2hv T3 1.022M eV T3 Rout unonr 2hv 1.022M eVRur T3 Q hv1 2m0c 2 2m0 c 2 hv1 tr T hv3 2m0 c 2 2m0 c 2 hv13 Rin u Rin c Rout c Rur 0 Rout u Rout unonr 2hv 1.022MeV Q hv trnet hv1 hv2 hv3 012pairannihilationproductionnettr1 hv 1.022 MeV T1 T2Exposure Historically, was introduced before kerma anddose, measured in roentgen (R) Defined as a quotientX dQdm dQ is absolute value of the total charge of the ionsof one sign produced in air when all electronsliberated by photons in air of mass dm arecompletely stopped in air Ionization from the absorption of radiative loss ofkinetic energy by electrons is not included8

Exposure Exposure is the ionization equivalent of thecollision kerma in air for x and g-rays Introduce mean energy expended in a gas perion pair formed, W , constant for each gas,independent of incoming photon energy For dry airWair33.97 eV/i.p. 1.602 10 19 J/eVe1.602 10 19 C/electron 33.97 J/CUnits of exposure The roentgen R is the customary unit The roentgen is defined as exposureproducing in air one unit of esu of chargeper 0.001293 g of air irradiated by thephotons. Conversion1R 1esu1C103 g 90.001293g 2.998 10 esu 1kgRelation of exposure to energyfluence Exposure at a point due to energy fluence ofmono-energetic photons e X en E ,air W air K c air e K c air / 33.97W air Units of [X] C/kg in SISignificance of exposure Energy fluence is proportional to exposurefor any given photon energy or spectrum Due to similarity in effective atomic number– Air can be made a tissue equivalent mediumwith respect to energy absorption – convenientin measurements– Collision kerma in muscle per unit of exposureis nearly independent of photon energy 2.580 10 4 C/kg1C/kg 3876 RSignificance of exposureSignificance of exposureRatio of mass energy-absorption coefficients for muscle/airand water/air are nearly constant (within 5%) for energiesfrom 4keV to 10 MeVRatio of mass energy-absorption coefficients for bone/air andacrylic/air are nearly constant for energies above 100keV9

Significance of exposureRadiation protection quantities X-ray field at a point can be characterizedby means of exposure regardless of whetherthere is air actually located at this point It implies that photon energy fluence at thatpoint is such that it would produce exposureof a stated value Same is applicable to kerma or collisionkerma, except that reference medium (notnecessarily air) has to be specified Quality factor Q – weighting factor to beapplied to absorbed dose to provide anestimate of the relative human hazard ofionizing radiation It is based on relative biologicaleffectiveness (RBE) of a particular radiationsource Q is dimensionlessRadiation protection quantitiesRadiation protection quantities Dose equivalent H, is defined asH DQN Here D – dose, Q- quality factor, N-productof modifiying factors (currently 1) Units of H: Higher-density charged particle tracks (higher collisionstopping power) are more damaging per unit dose– severs, Sv, if dose is expressed in J/kg– rem, if dose is in rad (10-2 J/kg)Summary Quantities describing the interaction ofionizing radiation with matter– Kerma, components of kerma– Absorbed dose– Exposure Relationship with fluence and energy fluence Quantities for use in radiation protection– Quality factor Q– Dose equivalent H10

Physics and Radiation Dosimetry Introduction Radiological physics studies ionizing radiation and its interaction with matter Began with discovery of x-rays, radioactivity and radium in 189

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