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

More documents

Recommendations

Info

SUMMARY Evaluation of Radiation Safety Measures 709 If the activity were to be dispersed by an explosion, it could possibly (but unlikely) be life threatening to persons in the immediate vicinity. There would be little or no risk of immediate health effects to persons beyond a few hundred meters. Category 2—The sources falling in this category are personally very dangerous. Being close to the unshielded source for time periods of minutes to hours could cause permanent injury; and the exposure could be fatal for time periods of hours to days. Dispersed category 2 activity is very unlikely to be life threatening in the immediate vicinity of the bomb after the explosion. It would be virtually impossible for this source to contaminate a public water supply to a dangerous level. Category 3—The sources in this category are personally dangerous. Permanent injury may be caused following nearby exposure to the unshielded source for several hours; and could possibly (but unlikely) be fatal for a person who is close to the unshielded source for a period of days to weeks. The dispersed activity is extremely unlikely to permanently injure or kill a person in the immediate vicinity, and there exists little or no risk of immediate health effects beyond a few meters from the explosion. Category 4—The sources in this category are unlikely to be dangerous. The dispersed activity of a category 4 source would not permanently injure anyone. Category 5—The sources in this category are not dangerous. No one would be permanently injured either from the source or from the dispersed activity. Engineering and administrative measures are employed in order to provide a safe working environment for radiation workers. However, since there is no guarantee that protective measures will never break down, we keep the working environment and the workers under continuing surveillance to verify that all the protective systems are operating as designed. Should a breakdown occur, then the surveillance system should detect it in the early stages of the breakdown. The workplace is monitored directly by two different methods: (1) by systematic and routine surveys that include measurement of external radiation, verification of the location and proper use of radiation sources, air sampling, and testing exposed surfaces for contamination, and (2) by fixed area monitors that continuously monitor external radiation fields and airborne radioactivity and have alarms that are preset to warn of high levels of radiation or airborne radioactivity. Individuals are monitored for external radiation with dosimeters, such as film badges, thermoluminescent dosimeters, and electronic dosimeters. For internally deposited radionuclides, workers are monitored by in vitro bioassay, in which the activity in excreta is measured, or by in vivo bioassay, in which the radiations originating in radionuclides inside the body are measured directly with appropriate counting instruments.
710 CHAPTER 13 Monitoring data must be properly interpreted if it is to make a positive contribution to the overall radiation safety program. To prevent authorized radioactive sources from falling into the hands of terrorists, the IAEA has formulated a code of practice that offers guidance on measures to be taken to secure the safety of radioactive sources. m Problems 13.1. A series of measurements with threshold detectors showed the following spectral distribution of neutrons: ENERGY PERCENT NEUTRONS Thermal 40 1000 eV 20 0.01 MeV 10 0.1 MeV 10 1 MeV 10 10 MeV 10 When 500-mg 32S was irradiated for 2 hours in this field and then counted in a 2π gas-flow counter 24 hours after the end of irradiation, the result was 500 cpm. What is the dose rate in this neutron field? 13.2. A sealed 90Sr source is leak-tested. The wipe, counted in a 2π gas-flow counter, gave 155 counts in 5 minutes. The background was 130 counts in 5 minutes. At the 95% confidence level, is the source contaminated? 13.3. An air sample on a filter paper was counted in a 2π gas-flow counter and gave 800 counts in 5 minutes. A background count gave 260 counts in 10 minutes. What was the standard deviation of the net counting rate? 13.4. A radioisotope worker weighing 70 kg inadvertently drank water containing 3.7 MBq (100 μCi) 22Na. Following this accidental exposure, his body burden was measured by whole-body counts made over a period of 2 months. The following retention function was fitted to the whole-body counting data: Q(t) = 1.8 exp(−0.082t) + 1.9 exp(−0.052t) MBq. Calculate (a) the cumulative activity, in Bq days. (b) the initial dose rate, assuming the 22Na to be uniformly distributed throughout the body (see Fig. 4-8 for 22Na transformation scheme). (c) the worker’s dose commitment.
Page 2 and 3:
INTRODUCTION TO Health Physics
Page 4 and 5:
INTRODUCTION TO Health Physics Herm
Page 6 and 7:
To my wife, Sylvia and to the memor
Page 8 and 9:
CONTENTS Preface/ XI 1. Introductio
Page 10 and 11:
Surface Contamination Limits/592 Wa
Page 12 and 13:
PREFACE The practice of radiation s
Page 14 and 15:
INTRODUCTION TO Health Physics
Page 16 and 17:
INTRODUCTION 1 Health physics, radi
Page 18 and 19:
REVIEW OF PHYSICAL PRINCIPLES MECHA
Page 20 and 21:
REVIEW OF PHYSICAL PRINCIPLES 5 In
Page 22 and 23:
and at v = 0.99 c, m = 9.11 × 10
Page 24 and 25:
REVIEW OF PHYSICAL PRINCIPLES 9 Sub
Page 26 and 27:
REVIEW OF PHYSICAL PRINCIPLES 11 Th
Page 28 and 29:
REVIEW OF PHYSICAL PRINCIPLES 13 co
Page 30 and 31:
Page 32 and 33:
REVIEW OF PHYSICAL PRINCIPLES 17 (t
Page 34 and 35:
Electrical Current: The Ampere REVI
Page 36 and 37:
Solution REVIEW OF PHYSICAL PRINCIP
Page 38 and 39:
REVIEW OF PHYSICAL PRINCIPLES 23 Ac
Page 40 and 41:
V a b REVIEW OF PHYSICAL PRINCIPLES
Page 42 and 43:
Elastic Collision REVIEW OF PHYSICA
Page 44 and 45:
Force Time REVIEW OF PHYSICAL PRINC
Page 46 and 47:
REVIEW OF PHYSICAL PRINCIPLES 31 5
Page 48 and 49:
REVIEW OF PHYSICAL PRINCIPLES 33 Fi
Page 50 and 51:
REVIEW OF PHYSICAL PRINCIPLES 35 In
Page 52 and 53:
Page 54 and 55:
or, in terms of the loss tangent,
Page 56 and 57:
where Impedance t = time after clos
Page 58 and 59:
Page 60 and 61:
REVIEW OF PHYSICAL PRINCIPLES 45 A
Page 62 and 63:
therefore, Matter Waves REVIEW OF P
Page 64 and 65:
Page 66 and 67:
SUMMARY REVIEW OF PHYSICAL PRINCIPL
Page 68 and 69:
REVIEW OF PHYSICAL PRINCIPLES 53 Ac
Page 70 and 71:
REVIEW OF PHYSICAL PRINCIPLES 55 2.
Page 72 and 73:
REVIEW OF PHYSICAL PRINCIPLES 57 2.
Page 74 and 75:
ATOMIC AND NUCLEAR STRUCTURE ATOMIC
Page 76 and 77:
Bohr’s Atomic Model ATOMIC AND NU
Page 78 and 79:
ATOMIC AND NUCLEAR STRUCTURE 63 2.
Page 80 and 81:
The energy of this photon is E = hc
Page 82 and 83:
ATOMIC AND NUCLEAR STRUCTURE 67 are
Page 84 and 85:
ATOMIC AND NUCLEAR STRUCTURE 69 ene
Page 86 and 87:
TABLE 3-1. Electronic Structure of
Page 88 and 89:
ATOMIC AND NUCLEAR STRUCTURE 73 rad
Page 90 and 91:
ATOMIC AND NUCLEAR STRUCTURE 75 spe
Page 92 and 93:
ATOMIC AND NUCLEAR STRUCTURE 77 whe
Page 94 and 95:
ATOMIC AND NUCLEAR STRUCTURE 79 neu
Page 96 and 97:
SUMMARY ATOMIC AND NUCLEAR STRUCTUR
Page 98 and 99:
ATOMIC AND NUCLEAR STRUCTURE 83 3.1
Page 100 and 101:
R ADIATION SOURCES RADIOACTIVITY 4
Page 102 and 103:
R ADIATION SOURCES 87 Figure 4-2. T
Page 104 and 105:
R ADIATION SOURCES 89 Figure 4-3. R
Page 106 and 107:
R ADIATION SOURCES 91 Figure 4-4. P
Page 108 and 109:
Figure 4-7. Iodine-131 transformati
Page 110 and 111:
R ADIATION SOURCES 95 Since positro
Page 112 and 113:
R ADIATION SOURCES 97 level of high
Page 114 and 115:
R ADIATION SOURCES 99 From the defi
Page 116 and 117:
R ADIATION SOURCES 101 determined b
Page 118 and 119:
R ADIATION SOURCES 103 sum of the l
Page 120 and 121:
R ADIATION SOURCES 105 of activity
Page 122 and 123:
Solution SA 14 10 226 × 1600 yea
Page 124 and 125:
and the number of radioactive atoms
Page 126 and 127:
W EXAMPLE 4.8 R ADIATION SOURCES 11
Page 128 and 129:
TABLE 4-2. Neptunium Series (4n +1)
Page 130 and 131:
TABLE 4-4. Actinium Series (4n +3)
Page 132 and 133:
R ADIATION SOURCES 117 TABLE 4-6. A
Page 134 and 135:
The integrand can be changed to the
Page 136 and 137:
Figure 4-14. Secular equilibrium: B
Page 138 and 139:
R ADIATION SOURCES 123 of the daugh
Page 140 and 141:
R ADIATION SOURCES 125 By the use o
Page 142 and 143:
Expanding and collecting terms, we
Page 144 and 145:
R ADIATION SOURCES 129 Figure 4-17.
Page 146 and 147:
Deflector Vacuum pump External deam
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 162 and 163:
Page 164 and 165:
Page 166 and 167:
Page 168 and 169:
Page 170 and 171:
TABLE 5-2. Bremsstrahlung Spectrum
Page 172 and 173:
Page 174 and 175:
Page 176 and 177:
Page 178 and 179:
Page 180 and 181:
Page 182 and 183:
Page 184 and 185:
Page 186 and 187:
W EXAMPLE 5.12 INTERACTION OF RADIA
Page 188 and 189:
Page 190 and 191:
Page 192 and 193:
Page 194 and 195:
Page 196 and 197:
Page 198 and 199:
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 206 and 207:
Page 208 and 209:
where INTERACTION OF RADIATION WITH
Page 210 and 211:
Page 212 and 213:
Page 214 and 215:
Page 216 and 217:
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
Page 238 and 239:
W Example 6.9 RADIATION DOSIMETRY 2
Page 240 and 241:
RADIATION DOSIMETRY 225 This calcul
Page 242 and 243:
where ϕ = intensity at depth t, ϕ
Page 244 and 245:
RADIATION DOSIMETRY 229 Assuming th
Page 246 and 247:
When we combine the constants in Eq
Page 248 and 249:
Solution RADIATION DOSIMETRY 233 Ph
Page 250 and 251:
RADIATION DOSIMETRY 235 In most ins
Page 252 and 253:
RADIATION DOSIMETRY 237 first-order
Page 254 and 255:
RADIATION DOSIMETRY 239 Integrating
Page 256 and 257:
Medical Internal Radiation Dose Met
Page 258 and 259:
RADIATION DOSIMETRY 243 1 Bq/cm 3 o
Page 260 and 261:
W Example 6.16 RADIATION DOSIMETRY
Page 262 and 263:
for 131I listed in the output data
Page 264 and 265:
then the total dose to the target o
Page 266 and 267:
251 TABLE 6-8. Absorbed Fractions (
Page 268 and 269:
RADIATION DOSIMETRY 253 which was f
Page 270 and 271:
255 TABLE 6-9. S, Absorbed Dose per
Page 272 and 273:
257 TABLE 6-10. S, Absorbed Dose Pe
Page 274 and 275:
RADIATION DOSIMETRY 259 values of S
Page 276 and 277:
RADIATION DOSIMETRY 261 S (kidney
Page 278 and 279:
RADIATION DOSIMETRY 263 and MIRD Pa
Page 280 and 281:
RADIATION DOSIMETRY 265 the 50-year
Page 282 and 283:
TABLE 6-11. Synthetic Tissue Compos
Page 284 and 285:
Solution Dn,p = The dose rate due t
Page 286 and 287:
RADIATION DOSIMETRY 271 6.2. An air
Page 288 and 289:
RADIATION DOSIMETRY 273 (a) Plot th
Page 290 and 291:
RADIATION DOSIMETRY 275 the averag
Page 292 and 293:
RADIATION DOSIMETRY 277 No. 7. Berg
Page 294 and 295:
7 BIOLOGICAL BASIS FOR RADIATION SA
Page 296 and 297:
BIOLOGICAL BASIS FOR R ADIATION SAF
Page 298 and 299:
Page 300 and 301:
Page 302 and 303:
Na + K + BIOLOGICAL BASIS FOR R ADI
Page 304 and 305:
Page 306 and 307:
Page 308 and 309:
Page 310 and 311:
TLC VC IC FRC IRV TV RV RV BIOLOGIC
Page 312 and 313:
Page 314 and 315:
Capillary knot Vein BIOLOGICAL BASI
Page 316 and 317:
Cell body One nerve cell Axon Nucle
Page 318 and 319:
Page 320 and 321:
Aqueous humor Cornea Iris Lens Vitr
Page 322 and 323:
Page 324 and 325:
Leucocytes and lymphocytes (x10 −
Page 326 and 327:
TABLE 7-5. Tissue Dose Rate vs. Dis
Page 328 and 329:
Birth Defects (Teratogenesis) BIOLO
Page 330 and 331:
Page 332 and 333:
Cancer BIOLOGICAL BASIS FOR R ADIAT
Page 334 and 335:
Page 336 and 337:
Page 338 and 339:
Incidence Incidence General form Do
Page 340 and 341:
Page 342 and 343:
Page 344 and 345:
Page 346 and 347:
Page 348 and 349:
Page 350 and 351:
Page 352 and 353:
RADIATION SAFETY GUIDES 8 Radiation
Page 354 and 355:
RADIATION SAFETY GUIDES 339 radiati
Page 356 and 357:
RADIATION SAFETY GUIDES 341 members
Page 358 and 359:
RADIATION SAFETY GUIDES 343 is a me
Page 360 and 361:
RADIATION SAFETY GUIDES 345 Figure
Page 362 and 363:
RADIATION SAFETY GUIDES 347 by radi
Page 364 and 365:
RADIATION SAFETY GUIDES 349 radiati
Page 366 and 367:
Dose Coefficient RADIATION SAFETY G
Page 368 and 369:
RADIATION SAFETY GUIDES 353 appropr
Page 370 and 371:
RADIATION SAFETY GUIDES 355 The cal
Page 372 and 373:
Airborne Radioactivity RADIATION SA
Page 374 and 375:
RADIATION SAFETY GUIDES 359 collisi
Page 376 and 377:
RADIATION SAFETY GUIDES 361 is 1 g/
Page 378 and 379:
Page 380 and 381:
RADIATION SAFETY GUIDES 365 can be
Page 382 and 383:
RADIATION SAFETY GUIDES 367 total w
Page 384 and 385:
RADIATION SAFETY GUIDES 369 TABLE 8
Page 386 and 387:
compartment after a time t is given
Page 388 and 389:
RADIATION SAFETY GUIDES 373 Now we
Page 390 and 391:
RADIATION SAFETY GUIDES 375 classi
Page 392 and 393:
RADIATION SAFETY GUIDES 377 normal
Page 394 and 395:
Page 396 and 397:
RADIATION SAFETY GUIDES 381 whose c
Page 398 and 399:
13 14 12 11 GI Tract 13 T RADIATION
Page 400 and 401:
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
Page 412 and 413:
RADIATION SAFETY GUIDES 397 nation
Page 414 and 415:
and the total activity in the body
Page 416 and 417:
RADIATION SAFETY GUIDES 401 segment
Page 418 and 419:
RADIATION SAFETY GUIDES 403 where E
Page 420 and 421:
TABLE 8-22. Radioisotopes That Do N
Page 422 and 423:
RADIATION SAFETY GUIDES 407 The sma
Page 424 and 425:
RADIATION SAFETY GUIDES 409 TABLE 8
Page 426 and 427:
RADIATION SAFETY GUIDES 411 Kentuck
Page 428 and 429:
RADIATION SAFETY GUIDES 413 The fra
Page 430 and 431:
RADIATION SAFETY GUIDES 415 ALI = 1
Page 432 and 433:
W Example 8.10 RADIATION SAFETY GUI
Page 434 and 435:
W Example 8.12 RADIATION SAFETY GUI
Page 436 and 437:
RADIATION SAFETY GUIDES 421 Substit
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 448 and 449:
Page 450 and 451:
Page 452 and 453:
TABLE 9-2. Scintillating Materials
Page 454 and 455:
Page 456 and 457:
Figure 9-10. Block diagram of a sin
Page 458 and 459:
Page 460 and 461:
Page 462 and 463:
DOSE-MEASURING INSTRUMENTS HEALTH P
Page 464 and 465:
Response Normalized to Cs-137 10 Co
Page 466 and 467:
Page 468 and 469:
Page 470 and 471:
Page 472 and 473:
Page 474 and 475:
Page 476 and 477:
Survey Meters: Ion Current Chambers
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
Page 484 and 485:
Page 486 and 487:
Page 488 and 489:
Page 490 and 491:
Count rate per unit flux 10 1 .1 .0
Page 492 and 493:
Page 494 and 495:
Solution HEALTH PHYSICS INSTRUMENTA
Page 496 and 497:
Neutrons TABLE 9-7. Calibration Sou
Page 498 and 499:
Page 500 and 501:
Accuracy HEALTH PHYSICS INSTRUMENTA
Page 502 and 503:
Page 504 and 505:
Page 506 and 507:
and is often expressed as a percent
Page 508 and 509:
Page 510 and 511:
Page 512 and 513:
Page 514 and 515:
W Example 9.16 What is the MDA for
Page 516 and 517:
Rearranging Eq. (9.60) and applying
Page 518 and 519:
For the data in this example: HEALT
Page 520 and 521:
Solution X = 1589 7 = 227 (Xi −
Page 522 and 523:
Page 524 and 525:
Page 526 and 527:
Page 528 and 529:
10 EXTERNAL RADIATION SAFETY BASIC
Page 530 and 531:
EXTERNAL RADIATION SAFETY 515 By th
Page 532 and 533:
W Example 10.2 EXTERNAL RADIATION S
Page 534 and 535:
EXTERNAL RADIATION SAFETY 519 Figur
Page 536 and 537:
Page 538 and 539:
Au 198 Ir 192 Cs 137 EXTERNAL RADIA
Page 540 and 541:
Dose buildup factor, B Dose buildup
Page 542 and 543:
EXTERNAL RADIATION SAFETY 527 layer
Page 544 and 545:
X-Rays EXTERNAL RADIATION SAFETY 52
Page 546 and 547:
EXTERNAL RADIATION SAFETY 531 recom
Page 548 and 549:
where EXTERNAL RADIATION SAFETY 533
Page 550 and 551:
535 TABLE 10-4. Values for the Para
Page 552 and 553:
EXTERNAL RADIATION SAFETY 537 a sec
Page 554 and 555:
Page 556 and 557:
TABLE 10-6. Commercial Lead Sheets
Page 558 and 559:
EXTERNAL RADIATION SAFETY 543 The o
Page 560 and 561:
EXTERNAL RADIATION SAFETY 545 Dist
Page 562 and 563:
EXTERNAL RADIATION SAFETY 547 by th
Page 564 and 565:
from Eqs. (10.26a) and (10.26b) int
Page 566 and 567:
EXTERNAL RADIATION SAFETY 551 TABLE
Page 568 and 569:
Transmission 1.0 86 4 2 10 8 6 4 -1
Page 570 and 571:
EXTERNAL RADIATION SAFETY 555 to 0.
Page 572 and 573:
The required lead-equivalent leaded
Page 574 and 575:
Wpri = primary barrier weekly workl
Page 576 and 577:
where EXTERNAL RADIATION SAFETY 561
Page 578 and 579:
W = workload, Gy/wk, T = occupancy
Page 580 and 581:
EXTERNAL RADIATION SAFETY 565 Gamm
Page 582 and 583:
where Ni = number of atoms of the i
Page 584 and 585:
EXTERNAL RADIATION SAFETY 569 which
Page 586 and 587:
EXTERNAL RADIATION SAFETY 571 is fo
Page 588 and 589:
where C = cost per unit volume of t
Page 590 and 591:
EXTERNAL RADIATION SAFETY 575 for a
Page 592 and 593:
EXTERNAL RADIATION SAFETY 577 Calcu
Page 594 and 595:
EXTERNAL RADIATION SAFETY 579 per
Page 596 and 597:
EXTERNAL RADIATION SAFETY 581 Patte
Page 598 and 599:
11 INTERNAL R ADIATION SAFETY INTER
Page 600 and 601:
INTERNAL RADIATION SAFETY 585 Figur
Page 602 and 603:
Page 604 and 605:
INTERNAL RADIATION SAFETY 589 regar
Page 606 and 607:
591 TABLE 11-3. Protection Factors
Page 608 and 609:
INTERNAL RADIATION SAFETY 593 the m
Page 610 and 611:
INTERNAL RADIATION SAFETY 595 TABLE
Page 612 and 613:
INTERNAL RADIATION SAFETY 597 the U
Page 614 and 615:
Page 616 and 617:
INTERNAL RADIATION SAFETY 601 effec
Page 618 and 619:
603 TABLE 11-7. Treatment Methods f
Page 620 and 621:
INTERNAL RADIATION SAFETY 605 or ba
Page 622 and 623:
Page 624 and 625:
Figure 11-5. Gaussian plume dispers
Page 626 and 627:
TABLE 11-10. Pasquill’s Categorie
Page 628 and 629:
INTERNAL RADIATION SAFETY 613 is 4
Page 630 and 631:
INTERNAL RADIATION SAFETY 615 Equat
Page 632 and 633:
INTERNAL RADIATION SAFETY 617 In ce
Page 634 and 635:
INTERNAL RADIATION SAFETY 619 In th
Page 636 and 637:
INTERNAL RADIATION SAFETY 621 Since
Page 638 and 639:
W Example 11.7 INTERNAL RADIATION S
Page 640 and 641:
INTERNAL RADIATION SAFETY 625 In th
Page 642 and 643:
INTERNAL RADIATION SAFETY 627 (b) A
Page 644 and 645:
INTERNAL RADIATION SAFETY 629 a = c
Page 646 and 647:
INTERNAL RADIATION SAFETY 631 treat
Page 648 and 649:
INTERNAL RADIATION SAFETY 633 activ
Page 650 and 651:
INTERNAL RADIATION SAFETY 635 Cohen
Page 652 and 653:
INTERNAL RADIATION SAFETY 637 Repor
Page 654 and 655:
CRITICALITY CRITICALITY HAZARD 12 O
Page 656 and 657:
Potential energy E11 E12Em 2r Dista
Page 658 and 659:
Fission Products CRITICALITY 643 Th
Page 660 and 661:
CRITICALITY A2 = 2.35 × 10 15 1.2
Page 662 and 663:
and will cause “fast fission.”
Page 664 and 665:
W Example 12.3 CRITICALITY 649 Calc
Page 666 and 667:
CRITICALITY 651 Making the very rea
Page 668 and 669:
TABLE 12-3. Delayed Neutrons from t
Page 670 and 671:
Power level dt t T τ then T = τ -
Page 672 and 673:
CRITICALITY 657 TABLE 12-5. Activit
Page 674 and 675: TABLE 12-6. Minimum Critical Mass o
Page 676 and 677: SUMMARY CRITICALITY 661 a criticali
Page 678 and 679: CRITICALITY 663 12.10. The blood pl
Page 680 and 681: CRITICALITY 665 Knief, R. A. Nuclea
Page 682 and 683: EVALUATION OF RADIATION SAFETY MEAS
Page 684 and 685: Evaluation of Radiation Safety Meas
Page 694 and 695: W EXAMPLE 13.4 Evaluation of Radiat
Page 716 and 717: W EXAMPLE 13.9 Evaluation of Radiat
Page 728 and 729: (b) Are the distributions normal or
Page 736 and 737: NONIONIZING RADIATION SAFETY 14 Non
Page 738 and 739: Solution NONIONIZING RADIATION SAFE
Page 740 and 741: NONIONIZING RADIATION SAFETY 725 hi
Page 742 and 743: 2.4 mW cm 2 E mW cm 2 = (50 cm)2 (1
Page 744 and 745: NONIONIZING RADIATION SAFETY 729 Fi
Page 746 and 747: NONIONIZING RADIATION SAFETY 731 Fi
Page 748 and 749: Figure 14-4. Beam cross sections fo
Page 750 and 751: % Total Transmission 100 90 80 70 6
Page 752 and 753: NONIONIZING RADIATION SAFETY 737 TA
Page 758 and 759: W Example 14.7 NONIONIZING RADIATIO
Page 760 and 761: NONIONIZING RADIATION SAFETY 745 Th
Page 762 and 763: TABLE 14-12. Reflecting Materials N
Page 764 and 765: Solution NONIONIZING RADIATION SAFE
Page 766 and 767: Solution The irradiance at the aper
Page 768 and 769: Wavelengths (nm) NONIONIZING RADIAT
Page 770 and 771: n = 300 pulses s × 10 seconds = 30
Page 772 and 773: % of Peak 100 80 60 40 20 NONIONIZI
Page 774 and 775:
NONIONIZING RADIATION SAFETY 759 Th
Page 776 and 777:
TABLE 14-16. Radar Bands FREQUENCY
Page 778 and 779:
NONIONIZING RADIATION SAFETY 763 Al
Page 780 and 781:
NONIONIZING RADIATION SAFETY 765 po
Page 782 and 783:
NONIONIZING RADIATION SAFETY 767 Gr
Page 784 and 785:
NONIONIZING RADIATION SAFETY 769 in
Page 786 and 787:
Since there is 1 J/s in a watt, 1.1
Page 788 and 789:
NONIONIZING RADIATION SAFETY 773 Th
Page 790 and 791:
Biological Effects NONIONIZING RADI
Page 792 and 793:
where Td = dry bulb temperature,
Page 794 and 795:
NONIONIZING RADIATION SAFETY 779 to
Page 796 and 797:
NONIONIZING RADIATION SAFETY 781 th
Page 798 and 799:
Dosimetry NONIONIZING RADIATION SAF
Page 800 and 801:
NONIONIZING RADIATION SAFETY 785 Fi
Page 802 and 803:
NONIONIZING RADIATION SAFETY 787 TA
Page 804 and 805:
where S = power density, W/m 2 , ε
Page 806 and 807:
NONIONIZING RADIATION SAFETY 791 ME
Page 808 and 809:
where A = attenuation, dB, t = shie
Page 810 and 811:
NONIONIZING RADIATION SAFETY 795 th
Page 812 and 813:
NONIONIZING RADIATION SAFETY 797 14
Page 814 and 815:
NONIONIZING RADIATION SAFETY 799 SO
Page 816 and 817:
NONIONIZING RADIATION SAFETY 801 Ha
Page 818 and 819:
APPENDIX A Values of Some Useful Co
Page 820 and 821:
APPENDIX B Table of the Elements NA
Page 822 and 823:
Table of the Elements (Continued) A
Page 824 and 825:
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.
Page 834 and 835:
Page 836 and 837:
Page 838 and 839:
Page 840 and 841:
Page 842 and 843:
Page 844 and 845:
Page 846 and 847:
Page 848 and 849:
Page 850 and 851:
Page 852 and 853:
Page 854 and 855:
Page 856 and 857:
Page 858 and 859:
Page 860 and 861:
845 Target 0.200 0.500 1.000 1.500
Page 862 and 863:
Page 864 and 865:
Page 866 and 867:
APPENDIX E TOTAL MASS ATTENUATION C
Page 868 and 869:
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
Page 884 and 885:
n-p junction, 445 Nuclear bombings
Page 886 and 887:
Radium injections, 324 Radon daught
Page 888:
Type 2, or non-insulin-dependent di
show all

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

Create successful ePaper yourself

Delete template?

Save as template?