basic physics concepts firas mourtada, ph.d. d. abr associate professor md anderson cancer center
TRANSCRIPT
Radioactive Decay
dN/dt = -N
dN/N = -dt
N(t) = N0e-t
N0 = initial number
N(t) = number at time t
= decay constant
half-life of 198Auhalf life 2.7 days
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Decay of Au198Half-life = 2.7 days
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Decay of Au198Half-life = 2.7 days
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Decay of Au198Half-life = 2.7 days
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Half - Lives
Isotope Half - Life226Ra 1620 years137Cs 30 years198Au 2.7 days192Ir 73.83 days125I 59.4 days103Pd 16.97 days
Au198 half-life vs mean lifeHalf-life = 2.7 days
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Brachytherapy Source Strength Specification
Sealed photon source Encapsulated so radioactive material can not be
lost from physical or chemical stress under foreseeable circumstances. Usually double metal wall encapsulation, prevents escape of radioactive material and absorbs unwanted betas.
All brachytherapy sources are sealed sources except 192Ir wire or hairpins, which have core exposed when cut. ISO considers 192Ir wire or hairpins to be a closed source.
Brachytherapy Source Strength Specification
Mass- Early 20th century
Activity- Early 20th century
Apparent Activity- Mid 20th century
Air Kerma Strength-Late 20th century
Mass
Radium– Mme. Curie prepared first 226Ra standards,
quantified amount by expressing mass of sample in g or mg.
Activity
226Ra alpha decays to 222Rn, all photons are emitted by radon or radon daughter products.
222Radon seeds produced by collecting radon gas from decay of radium and encapsulating in gold tubing.
Method needed to permit correlation of 222Rn to 226Ra clinical experience.
Activity
Defined 1 Curie (Ci) to be the amount of radon in equilibrium with 1 g of radium.
A 1 Ci radon seed has same activity as 1 g of radium.
Early experiments indicated 1 Ci of radon emitted 3.7 * 1010 alpha per second.
1 Ci defined as 3.7*1010 disintegrations per second (d.p.s.).
Activity
Later experiments established amount of radon in equilibrium with 1 g of radium gives 3.61 * 1010 d.p.s.
Curie definition remains 3.7 *1010 d.p.s. milliCurie (mCi) is 3.7 * 107 d.p.s.
Roughly, conversion is 27 mCi per 1 GBq
Apparent Activity
Apparent activity - activity of a bare source that produces the same exposure rate at calibration distance as the specified source.
Expressed in mCi for brachytherapy. Particularly useful for low energy photon
sources, e.g., 125I, 103Pd
mgRaeq
Post WWII, other reactor produced isotopes began to be used as radium substitutes in radiotherapy.
Source strength was expressed in mCi, but also needed a method to take advantage of clinical experience with radium.
Used mgRaeq.
mgRaeq
mgRaeq yields same exposure rate at calibration distance as 1 mg Ra encapsulated by 0.5mm Pt.
The exposure rate at 1 cm from 1 mg Ra(0.5mm) is 8.25R/hr.
Exposure Rate constant () is = 8.25 [(R-cm2)/(mg-hr)] - Ra(0.5mm Pt)
= 7.71 [(R-cm2)/(mg-hr)] - Ra(1.0mm Pt)
mg-hours or mgRaeq-hours
Number of mg or mgRaeq in implant times the duration of the implant in hours
Source Specification
Activity - mCi - 3.7 x 107 d.p.s.
Apparent activity - activity of a bare point source that produces same exposure rate at calibration distance as the specified source.
mg Ra eq - amount of 226Ra that produces same exposure rate at calibration distance as specified isotope
Exposure Rate Constants
Isotope (R-cm2/mCi-hr)226Ra (0.5mmPt) 8.25137Cs 3.3192Ir 4.69198Au 2.38125I 1.51103Pd 1.48
Conversion - mCi to mg Ra eq
Examples137Cs
# of mg Ra eq = (/) * # of mCi137Cs
= 0.4 * # of mCi137Cs
192Ir
# of mg Ra eq = (/) * # of mCi192Ir
= 0.569* # of mCi192Ir
1 mCi of 137Cs-dN / dt = 3.7 * 107 dps = NN = 3.7*107 dps / = 0.693 / T1/2 = 0.693 / (30 y * * 107 s/y) = 7.36 *10-10 s-1
N = 5.03 * 1016 atoms of 137Cs
A0 = 6.023 * 1023 atoms per 137 g (1 mole) of 137CsMass of 1mCi =
(5.03 * 1016 / 6.02 * 1023)*137 = 10 g
Dose Rate Calculation - Seeds
dD/dt = A f Btiss Bw Bs an /d2
activityexposure rate constantf = f-factor - R to cGy conversion factorBtiss = attenuation and scattering in tissue
w, s = attenuation and scattering for source encapsulation and self attenuation
an= anisotropy factord = distance to calculation point
Attenuation and Scattering Functions
TissueBtiss = 1+k(d)k
Btiss = + d + d2 +d3
WallBw = exp(-wtw)
SourceBs = exp(-sts)
Meisberger Coefficients
Ratio of in-water exposure to in-air exposure - Tissue attenuation/scattering
Meisberger, L.L., Keller, R., Shalek, R.J., The effective attenuation in water of gold-198, iridium-192, cesium-137, radium-226, and cobalt-60, Radiology 90, 953, 1968.
Meisberger ratio = A + Br + Cr^2 + Dr^3, r distance in cm from source to point of calculation
Cs137 Ir192 Au198 Ra226A 1.009100000 1.012800000 1.036000000 1.000500000B -0.009015000 0.005019000 -0.008134000 -0.004423000C -0.000345900 -0.001178000 0.001111000 -0.001707000D -0.000028170 -0.000020080 -0.000159700 0.000074480
r(cm) Cs137 Ir192 Au198 Ra2260.50000 1.00450 1.01501 1.03219 0.997871.00000 0.99971 1.01662 1.02882 0.994441.50000 0.99470 1.01761 1.02576 0.990282.00000 0.98946 1.01797 1.02290 0.985422.50000 0.98396 1.01767 1.02011 0.979943.00000 0.97818 1.01671 1.01729 0.973883.50000 0.97210 1.01508 1.01429 0.967304.00000 0.96570 1.01274 1.01102 0.960264.50000 0.95896 1.00970 1.00734 0.952825.00000 0.95186 1.00594 1.00314 0.94502
Meisberger Ratio
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distance from source(cm)
Do
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Cs137
Ir192
Au198
Ra226
Dose Rate Calculation - Linear Sources
Quantization Method - divide source into multiple point sources
Dose Rate Calculation - Linear Sources
Sievert Integral
L = active length
y = perpendicular distance from source to calculation point
= effective attenuation coefficient of wall
= as defined in diagram
2
1
dsec)texp(}Ly/)BBA{(dt/)y,x(dD stiss
% difference between 1.5cm Ra source and point Ra source
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distance(cm)
dist(cm) 1.5 cm AL point % diff0.25 50.67 126.23 59.86%0.50 20.26 31.51 35.71%0.75 10.84 13.98 22.48%1.00 6.67 7.85 15.05%1.50 3.20 3.47 7.91%2.00 1.85 1.95 4.89%2.50 1.20 1.24 3.06%3.00 0.83 0.85 2.85%3.50 0.61 0.62 2.16%4.00 0.47 0.47 0.81%4.50 0.37 0.37 0.40%5.00 0.30 0.30 -0.52%
cGy/mg-hr
Shalek and Stovall, American Journal of Roentgenology, Radium Therapy and Nuclear Medicine, CII, 662, 1968.
ACR Standard on Brachy Physics Manually-Loaded Temporary Implants Section IV.C.3.
An additional and independent method should be used to validate the dose calculation results of the computerized planning systems. This validation should be consistent with the written prescription and completed before 50% of the dose is delivered.
End of Lecture 1
Implant Doses
Permanent Implant
– D = (dD0/dt )Tav
Temporary Implant with T1/2>>T
– D = (dD0/dt ) T
Temporary Implant with T1/2 not >> T
– D = (dD0/dt ) Tav[1 - exp(-T/Tav)]
– “milliCuries destroyed”
Temporary Implant T1/2 not >>T
D = (dD0/dt)[-{exp(-t)}/{}]0t
D = (dD0/dt)[-{exp(-T)/} +{1/}]
D = ((dD0/dt) /)[1-exp(-T)]
D = (dD0/dt)Tav[1-exp(-T)]
D = (dD0/dt)Tav[1-exp(-T/Tav)]
t
00 dt)texp()dt/dD(D
milliCuries destroyed
D = (dD0/dt)Tav[1-exp(-T)]
D = (dD0/dt)Tav- (dD0/dt)exp(-T) Tav
D = (dD0/dt)Tav - (dDT/dt) Tav
Distance
For radiation protection purposes can assume dose follows inverse square law.
Dose at 1 cm = 4 * Dose @ 2cm
= 0.25 Dose @ 0.5cm
Photon Energies
Isotope Energies(MeV)226 Ra 0.047 - 2.45 (ave 0.83)137Cs 0.662192Ir 0.136 - 1.06 (ave 0.38)198Au 0.412125I 0.0274 - 0.0355 (ave 0.028)103Pd 0.0201, 0.023 (ave 0.021)