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

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INTERACTION OF RADIATION WITH M ATTER 181 where the three right-hand terms are the attenuation coefficients for the photoelectric effect, for Compton scattering, and for pair production, respectively. In computing attenuation of radiation for purposes of shielding design, the total attenuation coefficient as defined in Eq. (5.46) is used. Equation (5.46) gives the fraction of the energy in a beam that is removed, per unit absorber thickness. The fraction of the beam’s energy that is deposited in the absorber considers only the energy transferred to the absorber by the photoelectron, by the Compton electron, and by the electron pair. Energy carried away by the scattered photon in a Compton interaction and the energy carried off by the annihilation radiation after pair production is not included. The energy absorption coefficient, which is also called the true absorption coefficient, is given by hf − 1.02 μe = μpe + μCe + μpp (5.47) hf and is used in the calculation of radiation dose. The total attenuation and true absorption coefficients for air are shown in Figure 5-20, and the energy absorption coefficients for water, air, compact bone, and muscle are listed in Table 5-4. NEUTRONS Production The most prolific source of neutrons is the nuclear reactor. The splitting of a uranium or a plutonium nucleus in a nuclear reactor is accompanied by the emission of several Figure 5-20. Linear attenuation coefficients and absorption coefficients of air for gamma rays as a function of energy.
182 CHAPTER 5 TABLE 5-4. Values of the Mass Energy–Absorption Coefficients MASS-ENERGY-ABSORPTION COEFFICIENT (μen/ρ)cm2 PHOTON /g ENERGY Compact (MeV) Water Air Bone Muscle 0.010 4.89 4.66 19.0 4.96 0.015 1.32 1.29 5.89 1.36 0.020 0.523 0.516 2.51 0.544 0.030 0.147 0.147 0.743 0.154 0.040 0.0647 0.0640 0.0305 0.0677 0.050 0.0394 0.0384 0.158 0.0409 0.060 0.0304 0.0292 0.0979 0.0312 0.080 0.0253 0.0236 0.0520 0.0255 0.10 0.0252 0.0231 0.0386 0.0252 0.15 0.0278 0.0251 0.0304 0.0276 0.20 0.0300 0.0268 0.0302 0.0297 0.30 0.0320 0.0288 0.0311 0.0317 0.40 0.0329 0.0296 0.0316 0.0325 0.50 0.0330 0.0297 0.0316 0.0327 0.60 0.0329 0.0296 0.0315 0.0326 0.80 0.0321 0.0289 0.0306 0.0318 1.0 0.0311 0.0280 0.0297 0.0308 1.5 0.0283 0.0255 0.0270 0.0281 2.0 0.0260 0.0234 0.0248 0.0257 3.0 0.0227 0.0205 0.0219 0.0225 4.0 0.0205 0.0186 0.0199 0.0203 5.0 0.0190 0.0173 0.0186 0.0188 6.0 0.0180 0.0163 0.0178 0.0178 8.0 0.0165 0.0150 0.0165 0.0163 10.0 0.0155 0.0144 0.0159 0.0154 Source: FromPhysical Aspects of Irradiation. Washington, DC: US Government Printing Office; March 1964. NBS Handbook 85. neutrons. These fission neutrons have a wide range of energies, as shown in Figure 5-21. The distribution peaks at 0.7 MeV and has a mean value of 2 MeV. Except for several fission fragments of very short half-life, there are no radionuclides that decay by emitting neutrons. Californium-252, however, an alpha emitter, undergoes spontaneous nuclear fission at an average rate of 10 fissions for every 313 alpha transformations. Since the half-life of 252 Cf due to alpha emission is 2.73 years, its effective half-life, including spontaneous nuclear fission, is 2.65 years. Californium-252 thus simulates a neutron-emitting radionuclide. The neutron emission rate has been found to be 2.31 × 10 6 neutrons per second per μg 252 Cf. The emitted neutrons span a wide range of energies. The most probable energy is about 1 MeV, while the average value of the energy distribution is about 2.3 MeV. All other neutron sources depend on nuclear reactions for the emission of neutrons. Copious neutron beams may be produced in accelerators by many different reactions. For example, bombardment of beryllium by high-energy deuterons in a cyclotron produces neutrons according to the reaction 9 2 4Be + 1D → 11 5B ∗ 10 → 5B + 1 0n. (5.48)
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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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Page 148 and 149: Substituting the value of r from Eq
Page 150 and 151: R ADIATION SOURCES 135 before it is
Page 152 and 153: R ADIATION SOURCES 137 4.18. What w
Page 154 and 155: R ADIATION SOURCES 139 4.43. 100-mC
Page 156 and 157: R ADIATION SOURCES 141 Report No. 1
Page 158 and 159: INTERACTION OF RADIATION WITH MATTE
Page 160 and 161: INTERACTION OF RADIATION WITH M ATT
Page 170 and 171: TABLE 5-2. Bremsstrahlung Spectrum
Page 186 and 187: W EXAMPLE 5.12 INTERACTION OF RADIA
Page 200 and 201: Classification TABLE 5-6. α, n Neu
Page 202 and 203: W EXAMPLE 5.14 INTERACTION OF RADIA
Page 204 and 205: since ln E =−ξ, E 0 E E 0 = e
Page 208 and 209: where INTERACTION OF RADIATION WITH
Page 218 and 219: UNITS RADIATION DOSIMETRY 6 During
Page 220 and 221: Solution The radiation absorbed dos
Page 222 and 223: RADIATION DOSIMETRY 207 The relatio
Page 224 and 225: RADIATION DOSIMETRY 209 The use of
Page 226 and 227: RADIATION DOSIMETRY 211 Since one e
Page 228 and 229: RADIATION DOSIMETRY 213 Figure 6-5.
Page 230 and 231: The radiation absorbed dose rate fr
Page 232 and 233: RADIATION DOSIMETRY 217 Figure 6-6.
Page 234 and 235: 219 TABLE 6-1. Mean Mass Stopping P
Page 236 and 237: RADIATION DOSIMETRY 221 The exposur
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Page 240 and 241: RADIATION DOSIMETRY 225 This calcul
Page 242 and 243: where ϕ = intensity at depth t, ϕ
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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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Solution HEALTH PHYSICS INSTRUMENTA
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Neutrons TABLE 9-7. Calibration Sou
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Accuracy HEALTH PHYSICS INSTRUMENTA
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and is often expressed as a percent
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W Example 9.16 What is the MDA for
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Rearranging Eq. (9.60) and applying
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For the data in this example: HEALT
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Solution X = 1589 7 = 227 (Xi −
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10 EXTERNAL RADIATION SAFETY BASIC
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EXTERNAL RADIATION SAFETY 515 By th
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W Example 10.2 EXTERNAL RADIATION S
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EXTERNAL RADIATION SAFETY 519 Figur
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Au 198 Ir 192 Cs 137 EXTERNAL RADIA
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Dose buildup factor, B Dose buildup
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EXTERNAL RADIATION SAFETY 527 layer
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X-Rays EXTERNAL RADIATION SAFETY 52
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EXTERNAL RADIATION SAFETY 531 recom
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where EXTERNAL RADIATION SAFETY 533
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535 TABLE 10-4. Values for the Para
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EXTERNAL RADIATION SAFETY 537 a sec
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TABLE 10-6. Commercial Lead Sheets
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EXTERNAL RADIATION SAFETY 543 The o
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EXTERNAL RADIATION SAFETY 545 Dist
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EXTERNAL RADIATION SAFETY 547 by th
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from Eqs. (10.26a) and (10.26b) int
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EXTERNAL RADIATION SAFETY 551 TABLE
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Transmission 1.0 86 4 2 10 8 6 4 -1
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EXTERNAL RADIATION SAFETY 555 to 0.
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The required lead-equivalent leaded
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Wpri = primary barrier weekly workl
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where EXTERNAL RADIATION SAFETY 561
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W = workload, Gy/wk, T = occupancy
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EXTERNAL RADIATION SAFETY 565 Gamm
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where Ni = number of atoms of the i
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EXTERNAL RADIATION SAFETY 569 which
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EXTERNAL RADIATION SAFETY 571 is fo
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where C = cost per unit volume of t
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EXTERNAL RADIATION SAFETY 575 for a
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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
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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
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Chemical Composition APPENDIX C. 81
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Duration of Exposure 1. Occupationa
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APPENDIX D SPECIFIC ABSORBED FRACTI
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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
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ANSWERS TO PROBLEMS 2.1 0.53 m/s to
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TVL Al 5.3 cm 0.1 MeV Cu 0.6 cm
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12.2 Nuclide Bq/L pCi/mL 24 Na 1200
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INDEX Page numbers followed by “t
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Catecholamines, 303 Cavity ionizati
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Energy Research and Development Adm
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International Organization for Stan
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n-p junction, 445 Nuclear bombings
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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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