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

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HEALTH PHYSICS INSTRUMENTATION 433 Figure 9-5. Alpha and alpha–beta counting rates as a function of voltage in a proportional counter. Figure 9-5 shows the alpha and alpha–beta plateaus of a proportional counter. A GM counter too has a wide range of operating voltages over which the counting rate is approximately independent of the operating voltage. This plateau extends approximately from that voltage which results in pulses great enough to be passed by the discriminator to that which causes a rapid increase in counting rate that precedes an electrical breakdown of the counting gas. In the Geiger region, the avalanche is already extended as far as possible axially along the anode. Increasing the voltage, therefore, causes the avalanche to spread radially, resulting in an increasing counting rate. We therefore have a slight positive slope in the plateau, as shown in Figure 9-6. Figures of merit for judging the quality of a counter are the length of the plateau, the slope of the plateau, and the resolving time (discussed later). The slope is usually given as percentage increase in counting rate per 100 V: (C2 − C1) C1 Slope = × 100. (9.2) 0.01(V2 − V1) Figure 9-6. Operating characteristics of a Geiger-Müller counter.
434 CHAPTER 9 A GM counter has a slope of about 3% per 100 V. The operating voltage for a Geiger counter is about one-third to one-half the distance from the knee of the curve of count rate versus voltage. Quenching a GM Counter When the positive ions are collected after a pulse, they give up their kinetic energy by striking the wall of the tube. Most of this kinetic energy is dissipated as heat. Some of it, however, excites the atoms in the wall. In falling back to the ground state, these atoms may lose their excitation energy by emitting ultraviolet (UV) photons. Since at this time the electric field around the anode is reestablished to its full intensity, the interaction of UV photons with the gas in the counter may initiate an avalanche, and thereby produce a spurious count. Prevention of such spurious counts is called quenching. Quenching may be accomplished either electronically, by lowering the anode voltage after a pulse until all the positive ions have been collected, or chemically, by using a self-quenching gas. A self-quenching gas is one that can absorb the UV photons without becoming ionized. One method of doing this is to introduce a small amount of an organic vapor, such as alcohol or ether, into the tube. The energy from the UV photon is then dissipated in dissociating the organic molecule. Such a tube is useful only as long as it has a sufficient number of organic molecules for the quenching action. In practice, an organic-vapor GM counter has a useful life of about 10 8 counts. Self-quenching also results when the counting gas contains a trace of a halogen. In this case, the halogen molecule does not dissociate after absorbing the energy from the UV photon. The useful life of a halogen-quenched counter, therefore, is not limited by the number of pulses that have been produced in it. Resolving Time Resolving time is the minimum time interval between the arrival of two particles that the detector can recognize as two particles. If two particles enter the counter in rapid succession, the avalanche of ions from the first particle paralyzes the counter, and renders it incapable of responding to the second particle. The avalanche of ionization starts very close to the anode and spreads longitudinally along the anode because the electric-field intensity is greatest near the surface of the anode. The negative ions thus formed migrate toward the anode, while the positive ions move toward the cathode. The negative ions, being electrons, move very rapidly and are soon collected, while the massive positive ions are relatively slow-moving and therefore travel for a relatively long period of time before being collected. The collection time for positive ions formed near the surface of the anode is given by the equation (b t = 2 − a2 b )p × ln a seconds, (9.3) 2 × V μ where b = radius of cathode, cm; a = radius of anode, cm; p = gas pressure in counter, mm Hg;
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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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Page 400 and 401: RADIATION SAFETY GUIDES 385 Figure
Page 402 and 403: RADIATION SAFETY GUIDES 387 REGION
Page 404 and 405: RADIATION SAFETY GUIDES 389 The bb
Page 406 and 407: 391 TABLE 8-18. Values of Absorbed
Page 408 and 409: TABLE 8-19. Summary of Dose Calcula
Page 410 and 411: TABLE 8-20. Dose Coefficients for S
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Page 426 and 427: RADIATION SAFETY GUIDES 411 Kentuck
Page 428 and 429: RADIATION SAFETY GUIDES 413 The fra
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Page 432 and 433: W Example 8.10 RADIATION SAFETY GUI
Page 434 and 435: W Example 8.12 RADIATION SAFETY GUI
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Page 438 and 439: RADIATION SAFETY GUIDES 423 64. Inf
Page 440 and 441: RADIATION SAFETY GUIDES 425 16. Pro
Page 442 and 443: HEALTH PHYSICS INSTRUMENTATION RADI
Page 444 and 445: Gas-Filled Particle Counters HEALTH
Page 446 and 447: HEALTH PHYSICS INSTRUMENTATION 431
Page 452 and 453: TABLE 9-2. Scintillating Materials
Page 456 and 457: Figure 9-10. Block diagram of a sin
Page 462 and 463: DOSE-MEASURING INSTRUMENTS HEALTH P
Page 464 and 465: Response Normalized to Cs-137 10 Co
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Page 478 and 479: W Example 9.6 HEALTH PHYSICS INSTRU
Page 480 and 481: NEUTRON MEASUREMENTS HEALTH PHYSICS
Page 482 and 483: 467 TABLE 9-4. Threshold Foil React
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Page 494 and 495: Solution HEALTH PHYSICS INSTRUMENTA
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HEALTH PHYSICS INSTRUMENTATION 483
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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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