Introduction to Health Physics: Fourth Edition - Ruang Baca FMIPA UB

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EXTERNAL RADIATION SAFETY 527 layer (1 HVL) to account for buildup. The HVL of lead for 0.661-MeV gamma rays is HVL = ln 2 λ 0.693 = = 0.56 cm. 1.24 cm−1 The estimated shield thickness therefore is 3.84 plus 0.56, or 4.40 cm, which corresponds to 1.24 × 4.40 = 5.5 relaxation lengths. From Figure 10-9, we find (by interpolation) the dose-buildup factor for 0.661-MeV gamma rays to be 2.12 for a lead shield of this thickness. Substituting these values for B and t into Eq. (10.17), we have −1.24 × 4.4 I = 2890 × 2.12 × e = 26 μSv/h (2.6 mrems/h). This calculated reduction in gamma-ray dose rate is just slightly more than the desired value of 2.5 mR/h. The thickness of 4.4, as calculated above, is therefore just about correct. In this example, we found the correct thickness after one attempt in a trial-and-error method. If the calculated reduction in radiation dose rate had not turned out to be so close to the design value with the estimated shield thickness, we would have continued, by trial and error, to estimate thicknesses until the one that results in the desired reduction of dose rate would have been obtained. W Example 10.5 Design a spherical, lead storage container that will attenuate the exposure rate from 1Ciof 24 Na to 10 mR/h at a distance of 1 m from the source. Solution In each disintegration of a 24 Na atom, two gamma rays are emitted in cascade: one of 2.75 MeV and one of 1.37 MeV. The dose rate, at a distance of 1 m, due to each of these photons is, from Eq. (6.18): Ɣ2.75 = 0.5 × 2.75 = 1.38 Ɣ1.37 = 0.5 × 1.37 = 0.69 R · m2 C · h , R · m2 C · h . To reduce the exposure rate from the high-energy photon to 10 mR/h for the condition of good geometry, we use the interpolated value of 0.485 cm −1 (Table 5-3) for the attenuation coefficient μ. I = I0 10 −0.485t = e 1380 t = 10.16 cm.
528 CHAPTER 10 The HVL of lead for 2.75-MeV gammas is 1.43 cm. To account for the 1.37-MeV gamma, let us add one-half an HVL, or 0.72 cm, to the thickness calculated above for the 2.75-MeV gamma. We will then calculate the attenuation of the 2.75-MeV gamma with the new trial thickness, 10.16 + 0.72 = 10.88 cm. −0.485 × 10.88 I = 1380 × e I = 7.1mR/h. With this thickness of lead, the 1.37-MeV gamma, whose attenuation coefficient is 0.629 cm −1 (Table 5-2) will be attenuated to −0.629 × 10.88 I = 690 × e I = 0.7mR/h, and the total exposure rate at a distance of 1 m will be the sum of the exposure rates due to the two quantum energies, or 7.8 mR/h. The calculation above is based on good geometry. Let us now account for buildup in the shield. Considering at this time only the high-energy photon, let us add another half of one HVL to the shield thickness, which gives us 11.6 cm. Since one relaxation length of lead for 2.75-MeV gammas is 2.1 cm, the shield thickness corresponds to 5.5 relaxation lengths. From Figure 10-9, we find the buildup factor to be 3.1. The attenuation of the shield, therefore, according to Eq. (10.17), is I = 1380 × 3.1 × e −0.485×11.6 I = 15.4 mR/h. This exposure rate is too high; the shield thickness must therefore be increased. If we add another HVL to the shield to give us 13 cm, or 6.3 relaxation lengths, and using the corresponding dose buildup factor of 3.4, we find the exposure rate to be 8.5 mR/h for the high-energy photon. For the lower-energy photon, whose relaxation length in lead is 1.6 cm, this shield thickness corresponds to 8.2 relaxation lengths, and the dose buildup factor is 3.6. With these values in Eq. (10.17), the exposure rate due to the 1.37-MeV photons is calculated as 0.7 mR/h. The total exposure rate at a distance of 1 m from the shielded 24 Na source is thus 9.2 mR/h. Since this rate may be considered, for most practical purposes, to be equivalent to the design value of 10 mR/h, the required shield thickness is 13 cm. Since the shield may be interposed anywhere between the source and the point where the desired attenuated dose rate is located, and since the volume of lead, for a given wall thickness in a spherical shield, increases rapidly with increasing outer radius according to the expression Volume = 4 3 π(r 3 0 − r 3 1 ), the inner radius of the shield is kept as small as possible, consistent with the space requirements set by the physical dimensions of the source. The outside radius then is equal to the sum of the inside radius and the shield thickness.
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INTRODUCTION TO Health Physics
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INTRODUCTION TO Health Physics Herm
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To my wife, Sylvia and to the memor
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CONTENTS Preface/ XI 1. Introductio
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Surface Contamination Limits/592 Wa
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PREFACE The practice of radiation s
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INTRODUCTION TO Health Physics
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INTRODUCTION 1 Health physics, radi
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REVIEW OF PHYSICAL PRINCIPLES MECHA
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REVIEW OF PHYSICAL PRINCIPLES 5 In
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and at v = 0.99 c, m = 9.11 × 10
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REVIEW OF PHYSICAL PRINCIPLES 9 Sub
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REVIEW OF PHYSICAL PRINCIPLES 11 Th
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REVIEW OF PHYSICAL PRINCIPLES 13 co
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REVIEW OF PHYSICAL PRINCIPLES 17 (t
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Electrical Current: The Ampere REVI
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Solution REVIEW OF PHYSICAL PRINCIP
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REVIEW OF PHYSICAL PRINCIPLES 23 Ac
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V a b REVIEW OF PHYSICAL PRINCIPLES
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Elastic Collision REVIEW OF PHYSICA
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Force Time REVIEW OF PHYSICAL PRINC
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REVIEW OF PHYSICAL PRINCIPLES 31 5
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REVIEW OF PHYSICAL PRINCIPLES 33 Fi
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REVIEW OF PHYSICAL PRINCIPLES 35 In
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or, in terms of the loss tangent,
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where Impedance t = time after clos
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REVIEW OF PHYSICAL PRINCIPLES 45 A
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therefore, Matter Waves REVIEW OF P
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SUMMARY REVIEW OF PHYSICAL PRINCIPL
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REVIEW OF PHYSICAL PRINCIPLES 53 Ac
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REVIEW OF PHYSICAL PRINCIPLES 55 2.
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REVIEW OF PHYSICAL PRINCIPLES 57 2.
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ATOMIC AND NUCLEAR STRUCTURE ATOMIC
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Bohr’s Atomic Model ATOMIC AND NU
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ATOMIC AND NUCLEAR STRUCTURE 63 2.
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The energy of this photon is E = hc
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ATOMIC AND NUCLEAR STRUCTURE 67 are
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ATOMIC AND NUCLEAR STRUCTURE 69 ene
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TABLE 3-1. Electronic Structure of
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ATOMIC AND NUCLEAR STRUCTURE 73 rad
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ATOMIC AND NUCLEAR STRUCTURE 75 spe
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ATOMIC AND NUCLEAR STRUCTURE 77 whe
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ATOMIC AND NUCLEAR STRUCTURE 79 neu
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SUMMARY ATOMIC AND NUCLEAR STRUCTUR
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ATOMIC AND NUCLEAR STRUCTURE 83 3.1
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R ADIATION SOURCES RADIOACTIVITY 4
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R ADIATION SOURCES 87 Figure 4-2. T
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R ADIATION SOURCES 89 Figure 4-3. R
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R ADIATION SOURCES 91 Figure 4-4. P
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Figure 4-7. Iodine-131 transformati
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R ADIATION SOURCES 95 Since positro
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R ADIATION SOURCES 97 level of high
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R ADIATION SOURCES 99 From the defi
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R ADIATION SOURCES 101 determined b
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R ADIATION SOURCES 103 sum of the l
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R ADIATION SOURCES 105 of activity
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Solution SA 14 10 226 × 1600 yea
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and the number of radioactive atoms
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W EXAMPLE 4.8 R ADIATION SOURCES 11
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TABLE 4-2. Neptunium Series (4n +1)
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TABLE 4-4. Actinium Series (4n +3)
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R ADIATION SOURCES 117 TABLE 4-6. A
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The integrand can be changed to the
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Figure 4-14. Secular equilibrium: B
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R ADIATION SOURCES 123 of the daugh
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R ADIATION SOURCES 125 By the use o
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Expanding and collecting terms, we
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R ADIATION SOURCES 129 Figure 4-17.
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Deflector Vacuum pump External deam
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Substituting the value of r from Eq
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R ADIATION SOURCES 135 before it is
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R ADIATION SOURCES 137 4.18. What w
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R ADIATION SOURCES 139 4.43. 100-mC
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R ADIATION SOURCES 141 Report No. 1
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INTERACTION OF RADIATION WITH MATTE
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INTERACTION OF RADIATION WITH M ATT
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TABLE 5-2. Bremsstrahlung Spectrum
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W EXAMPLE 5.12 INTERACTION OF RADIA
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Classification TABLE 5-6. α, n Neu
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W EXAMPLE 5.14 INTERACTION OF RADIA
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since ln E =−ξ, E 0 E E 0 = e
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where INTERACTION OF RADIATION WITH
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UNITS RADIATION DOSIMETRY 6 During
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Solution The radiation absorbed dos
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RADIATION DOSIMETRY 207 The relatio
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RADIATION DOSIMETRY 209 The use of
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RADIATION DOSIMETRY 211 Since one e
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RADIATION DOSIMETRY 213 Figure 6-5.
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The radiation absorbed dose rate fr
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RADIATION DOSIMETRY 217 Figure 6-6.
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219 TABLE 6-1. Mean Mass Stopping P
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RADIATION DOSIMETRY 221 The exposur
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W Example 6.9 RADIATION DOSIMETRY 2
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RADIATION DOSIMETRY 225 This calcul
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where ϕ = intensity at depth t, ϕ
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RADIATION DOSIMETRY 229 Assuming th
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When we combine the constants in Eq
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Solution RADIATION DOSIMETRY 233 Ph
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RADIATION DOSIMETRY 235 In most ins
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RADIATION DOSIMETRY 237 first-order
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RADIATION DOSIMETRY 239 Integrating
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Medical Internal Radiation Dose Met
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RADIATION DOSIMETRY 243 1 Bq/cm 3 o
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W Example 6.16 RADIATION DOSIMETRY
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for 131I listed in the output data
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then the total dose to the target o
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251 TABLE 6-8. Absorbed Fractions (
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RADIATION DOSIMETRY 253 which was f
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255 TABLE 6-9. S, Absorbed Dose per
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257 TABLE 6-10. S, Absorbed Dose Pe
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RADIATION DOSIMETRY 259 values of S
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RADIATION DOSIMETRY 261 S (kidney
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RADIATION DOSIMETRY 263 and MIRD Pa
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RADIATION DOSIMETRY 265 the 50-year
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TABLE 6-11. Synthetic Tissue Compos
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Solution Dn,p = The dose rate due t
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RADIATION DOSIMETRY 271 6.2. An air
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RADIATION DOSIMETRY 273 (a) Plot th
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RADIATION DOSIMETRY 275 the averag
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RADIATION DOSIMETRY 277 No. 7. Berg
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7 BIOLOGICAL BASIS FOR RADIATION SA
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BIOLOGICAL BASIS FOR R ADIATION SAF
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Na + K + BIOLOGICAL BASIS FOR R ADI
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TLC VC IC FRC IRV TV RV RV BIOLOGIC
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Capillary knot Vein BIOLOGICAL BASI
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Cell body One nerve cell Axon Nucle
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Aqueous humor Cornea Iris Lens Vitr
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Leucocytes and lymphocytes (x10 −
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TABLE 7-5. Tissue Dose Rate vs. Dis
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Birth Defects (Teratogenesis) BIOLO
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Cancer BIOLOGICAL BASIS FOR R ADIAT
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Incidence Incidence General form Do
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RADIATION SAFETY GUIDES 8 Radiation
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RADIATION SAFETY GUIDES 339 radiati
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RADIATION SAFETY GUIDES 341 members
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RADIATION SAFETY GUIDES 343 is a me
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RADIATION SAFETY GUIDES 345 Figure
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RADIATION SAFETY GUIDES 347 by radi
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RADIATION SAFETY GUIDES 349 radiati
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Dose Coefficient RADIATION SAFETY G
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RADIATION SAFETY GUIDES 353 appropr
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RADIATION SAFETY GUIDES 355 The cal
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Airborne Radioactivity RADIATION SA
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RADIATION SAFETY GUIDES 359 collisi
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RADIATION SAFETY GUIDES 361 is 1 g/
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RADIATION SAFETY GUIDES 365 can be
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RADIATION SAFETY GUIDES 367 total w
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RADIATION SAFETY GUIDES 369 TABLE 8
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compartment after a time t is given
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RADIATION SAFETY GUIDES 373 Now we
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RADIATION SAFETY GUIDES 375 classi
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RADIATION SAFETY GUIDES 377 normal
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RADIATION SAFETY GUIDES 381 whose c
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13 14 12 11 GI Tract 13 T RADIATION
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RADIATION SAFETY GUIDES 387 REGION
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RADIATION SAFETY GUIDES 389 The bb
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391 TABLE 8-18. Values of Absorbed
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TABLE 8-19. Summary of Dose Calcula
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TABLE 8-20. Dose Coefficients for S
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RADIATION SAFETY GUIDES 397 nation
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and the total activity in the body
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RADIATION SAFETY GUIDES 401 segment
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RADIATION SAFETY GUIDES 403 where E
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TABLE 8-22. Radioisotopes That Do N
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RADIATION SAFETY GUIDES 407 The sma
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RADIATION SAFETY GUIDES 409 TABLE 8
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RADIATION SAFETY GUIDES 411 Kentuck
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RADIATION SAFETY GUIDES 413 The fra
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RADIATION SAFETY GUIDES 415 ALI = 1
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W Example 8.10 RADIATION SAFETY GUI
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W Example 8.12 RADIATION SAFETY GUI
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RADIATION SAFETY GUIDES 421 Substit
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RADIATION SAFETY GUIDES 423 64. Inf
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RADIATION SAFETY GUIDES 425 16. Pro
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HEALTH PHYSICS INSTRUMENTATION RADI
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Gas-Filled Particle Counters HEALTH
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HEALTH PHYSICS INSTRUMENTATION 431
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TABLE 9-2. Scintillating Materials
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Figure 9-10. Block diagram of a sin
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DOSE-MEASURING INSTRUMENTS HEALTH P
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Response Normalized to Cs-137 10 Co
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Survey Meters: Ion Current Chambers
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W Example 9.6 HEALTH PHYSICS INSTRU
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NEUTRON MEASUREMENTS HEALTH PHYSICS
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467 TABLE 9-4. Threshold Foil React
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Count rate per unit flux 10 1 .1 .0
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Page 494 and 495: Solution HEALTH PHYSICS INSTRUMENTA
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Page 530 and 531: EXTERNAL RADIATION SAFETY 515 By th
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EXTERNAL RADIATION SAFETY 577 Calcu
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EXTERNAL RADIATION SAFETY 579 per
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EXTERNAL RADIATION SAFETY 581 Patte
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11 INTERNAL R ADIATION SAFETY INTER
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INTERNAL RADIATION SAFETY 585 Figur
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INTERNAL RADIATION SAFETY 589 regar
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591 TABLE 11-3. Protection Factors
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INTERNAL RADIATION SAFETY 593 the m
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INTERNAL RADIATION SAFETY 595 TABLE
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INTERNAL RADIATION SAFETY 597 the U
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INTERNAL RADIATION SAFETY 601 effec
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603 TABLE 11-7. Treatment Methods f
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INTERNAL RADIATION SAFETY 605 or ba
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Figure 11-5. Gaussian plume dispers
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TABLE 11-10. Pasquill’s Categorie
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INTERNAL RADIATION SAFETY 613 is 4
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INTERNAL RADIATION SAFETY 615 Equat
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INTERNAL RADIATION SAFETY 617 In ce
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INTERNAL RADIATION SAFETY 619 In th
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INTERNAL RADIATION SAFETY 621 Since
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W Example 11.7 INTERNAL RADIATION S
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INTERNAL RADIATION SAFETY 625 In th
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INTERNAL RADIATION SAFETY 627 (b) A
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INTERNAL RADIATION SAFETY 629 a = c
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INTERNAL RADIATION SAFETY 631 treat
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INTERNAL RADIATION SAFETY 633 activ
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INTERNAL RADIATION SAFETY 635 Cohen
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INTERNAL RADIATION SAFETY 637 Repor
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CRITICALITY CRITICALITY HAZARD 12 O
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Potential energy E11 E12Em 2r Dista
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Fission Products CRITICALITY 643 Th
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CRITICALITY A2 = 2.35 × 10 15 1.2
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and will cause “fast fission.”
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W Example 12.3 CRITICALITY 649 Calc
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CRITICALITY 651 Making the very rea
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TABLE 12-3. Delayed Neutrons from t
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Power level dt t T τ then T = τ -
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CRITICALITY 657 TABLE 12-5. Activit
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TABLE 12-6. Minimum Critical Mass o
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SUMMARY CRITICALITY 661 a criticali
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CRITICALITY 663 12.10. The blood pl
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CRITICALITY 665 Knief, R. A. Nuclea
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EVALUATION OF RADIATION SAFETY MEAS
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Evaluation of Radiation Safety Meas
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W EXAMPLE 13.4 Evaluation of Radiat
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W EXAMPLE 13.9 Evaluation of Radiat
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SUMMARY Evaluation of Radiation Saf
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(b) Are the distributions normal or
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NONIONIZING RADIATION SAFETY 14 Non
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Solution NONIONIZING RADIATION SAFE
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NONIONIZING RADIATION SAFETY 725 hi
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2.4 mW cm 2 E mW cm 2 = (50 cm)2 (1
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NONIONIZING RADIATION SAFETY 729 Fi
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Figure 14-4. Beam cross sections fo
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% Total Transmission 100 90 80 70 6
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NONIONIZING RADIATION SAFETY 737 TA
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W Example 14.7 NONIONIZING RADIATIO
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NONIONIZING RADIATION SAFETY 745 Th
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TABLE 14-12. Reflecting Materials N
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Solution NONIONIZING RADIATION SAFE
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Solution The irradiance at the aper
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Wavelengths (nm) NONIONIZING RADIAT
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n = 300 pulses s × 10 seconds = 30
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% of Peak 100 80 60 40 20 NONIONIZI
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TABLE 14-16. Radar Bands FREQUENCY
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NONIONIZING RADIATION SAFETY 763 Al
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NONIONIZING RADIATION SAFETY 765 po
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NONIONIZING RADIATION SAFETY 767 Gr
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NONIONIZING RADIATION SAFETY 769 in
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Since there is 1 J/s in a watt, 1.1
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Biological Effects NONIONIZING RADI
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where Td = dry bulb temperature,
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NONIONIZING RADIATION SAFETY 779 to
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NONIONIZING RADIATION SAFETY 781 th
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Dosimetry NONIONIZING RADIATION SAF
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where S = power density, W/m 2 , ε
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NONIONIZING RADIATION SAFETY 791 ME
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where A = attenuation, dB, t = shie
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NONIONIZING RADIATION SAFETY 795 th
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NONIONIZING RADIATION SAFETY 797 14
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NONIONIZING RADIATION SAFETY 799 SO
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NONIONIZING RADIATION SAFETY 801 Ha
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APPENDIX A Values of Some Useful Co
Page 820 and 821:
APPENDIX B Table of the Elements NA
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Table of the Elements (Continued) A
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APPENDIX C The Reference Person Ove
Page 826 and 827:
Chemical Composition APPENDIX C. 81
Page 828 and 829:
Duration of Exposure 1. Occupationa
Page 830 and 831:
APPENDIX D SPECIFIC ABSORBED FRACTI
Page 832 and 833:
817 Energy in (MeV) Target 0.200 0.
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845 Target 0.200 0.500 1.000 1.500
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APPENDIX E TOTAL MASS ATTENUATION C
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APPENDIX F MASS ENERGY ABSORPTION C
Page 870 and 871:
ANSWERS TO PROBLEMS 2.1 0.53 m/s to
Page 872 and 873:
TVL Al 5.3 cm 0.1 MeV Cu 0.6 cm
Page 874 and 875:
12.2 Nuclide Bq/L pCi/mL 24 Na 1200
Page 876 and 877:
INDEX Page numbers followed by “t
Page 878 and 879:
Catecholamines, 303 Cavity ionizati
Page 880 and 881:
Energy Research and Development Adm
Page 882 and 883:
International Organization for Stan
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n-p junction, 445 Nuclear bombings
Page 886 and 887:
Radium injections, 324 Radon daught
Page 888:
Type 2, or non-insulin-dependent di
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Introduction to Health Physics: Fourth Edition - Ruang Baca FMIPA UB

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