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E-raamat: Physics for Radiation Protection 3e 3rd Edition [Wiley Online]

(University of Michigan)
  • Formaat: 670 pages
  • Ilmumisaeg: 13-Mar-2013
  • Kirjastus: Blackwell Verlag GmbH
  • ISBN-10: 3527667067
  • ISBN-13: 9783527667062
Teised raamatud teemal:
  • Wiley Online
  • Hind: 197,66 €*
  • * hind, mis tagab piiramatu üheaegsete kasutajate arvuga ligipääsu piiramatuks ajaks
Physics for Radiation Protection 3e 3rd EditionSuurem pilt
  • Formaat: 670 pages
  • Ilmumisaeg: 13-Mar-2013
  • Kirjastus: Blackwell Verlag GmbH
  • ISBN-10: 3527667067
  • ISBN-13: 9783527667062
Teised raamatud teemal:
Wiley Online e-raamatudRohkem infot Wiley Online kohta
Raamatu kodulehekülg: https://onlinelibrary.wiley.com/doi/book/10.1002/9783527667062
This third edition text and reference provides comprehensive treatment of the physics concepts that radiation protection professionals need to know. Coverage encompasses the structure of atoms, energy, radioactive transformation, interactions, nuclear fission and its products, interactions of radiation with matter, shielding, environmental dispersion, and detection and measurement, among other topics. Some familiarity with calculus is optimal. Martin (emeritus, radiation health, U. of Michigan) has devoted his long career to environmental assessment of radioactive materials, protection standards, and research and teaching on environmental and public health aspects of radiation physics. Annotation ©2013 Book News, Inc., Portland, OR (booknews.com)

A practical guide for health physicists and other radiation protection professionals.
This much-needed working resource presents clear, thorough, up-to-date explanations of the basic physics necessary to address real-world problems in radiation protection. Designed for readers with limited as well as basic science backgrounds, the text emphasizes applied concepts and carefully illustrates all topics through examples as well as practice problems.
Physics for Radiation Protection draws substantially on current resource data available for health physics use, providing decay schemes and emission energies for approximately 100 of the most common radionuclides encountered by practitioners. Excerpts from the Chart of the Nuclides, activation cross sections, fission yields, fission-product chains, photon attenuation coefficients, and nuclear masses are also provided. Coverage includes:
* The atom as an energy system
* An overview of the major discoveries in radiation physics
* Extensive discussion of radioactivity, including sources and materials
* Nuclear interactions and processes of radiation dose
* Calculational methods for radiation exposure, dose, and shielding
* Nuclear fission and production of activation and fission products
* Specialty topics ranging from nuclear criticality and applied statistics to digital imaging
* Extensive and current resource data cross-referenced to standard compendiums
* Recent critical events
* Extensive appendices and more than 400 figures
This complete discussion of the basic concepts allows readers to advance their professional skills.
Preface xvii
1 Structure of Atoms
1(10)
1.1 Atom Constituents
2(3)
1.2 Structure, Identity, and Stability of Atoms
5(1)
1.3 Chart of the Nuclides
6(2)
1.4 Nuclear Models
8(3)
Problems
Chapter 1
9(2)
2 Atoms and Energy
11(10)
2.1 Atom Measures
12(2)
2.2 Energy Concepts for Atoms
14(4)
2.2.1 Mass-energy
15(1)
2.2.2 Binding Energy of Nuclei
16(2)
2.3 Summary
18(3)
Other Suggested Sources
18(1)
Problems
Chapter 2
19(2)
3 Radioactive Transformation
21(70)
3.1 Processes of Radioactive Transformation
21(33)
3.1.1 Transformation of Neutron-rich Radioactive Nuclei
23(4)
3.1.2 Double Beta (ββ) Transformation
27(1)
3.1.3 Transformation of Proton-rich Nuclei
27(2)
3.1.4 Positron Emission
29(3)
3.1.5 Average Energy of Negatron and Positron Emitters
32(1)
3.1.6 Electron Capture (EC)
33(2)
3.1.7 Radioactive Transformation of Heavy Nuclei by Alpha Particle Emission
35(3)
3.1.8 Theory of Alpha Particle Transformation
38(2)
3.1.9 Transuranic (TRU) Radionuclides
40(1)
3.1.10 Gamma Emission
41(1)
3.1.11 Internal Transition (Metastable or Isomeric States)
42(1)
3.1.12 Internal Conversion
43(6)
3.1.13 Multiple Modes of Radioactive Transformation
49(2)
3.1.14 Transformation by Delayed Neutron Emission
51(1)
3.1.15 Transformation by Spontaneous Fission
51(2)
3.1.16 Proton Emission
53(1)
3.2 Decay Schemes
54(3)
3.3 Rate of Radioactive Transformation
57(8)
3.3.1 Activity
58(1)
3.3.2 Units of Radioactive Transformation
58(2)
3.3.3 Mathematics of Radioactive Transformation
60(2)
3.3.4 Half-Life
62(1)
3.3.5 Mean Life
63(1)
3.3.6 Effective Half-life
64(1)
3.4 Radioactivity Calculations
65(5)
3.4.1 Half-life Determination
68(2)
3.5 Activity-mass Relationships
70(3)
3.5.1 Specific Activity
70(3)
3.6 Radioactive Series Transformation
73(4)
3.6.1 Series Decay Calculations
73(3)
3.6.2 Recursive Kinetics: the Bateman Equations
76(1)
3.7 Radioactive Equilibrium
77(7)
3.7.1 Secular Equilibrium
78(2)
3.7.2 Transient Equilibrium
80(1)
3.7.3 Radionuclide Generators
81(3)
3.8 Total Number of Transformations (Uses of τ and λEff)
84(2)
3.9 Discovery of the Neutrino
86(5)
Acknowledgments
87(1)
Other Suggested Sources
87(1)
Problems
Chapter 3
88(3)
4 Interactions
91(52)
4.1 Production of X-rays
91(2)
4.2 Characteristic X-rays
93(5)
4.2.1 X-rays and Atomic Structure
95(1)
4.2.2 Auger Electrons
96(2)
4.3 Nuclear Interactions
98(6)
4.3.1 Cross-Section
100(2)
4.3.2 Q-values for Nuclear Reactions
102(2)
4.4 Alpha Particle Interactions
104(2)
4.4.1 Alpha-Neutron Reactions
105(1)
4.5 Transmutation by Protons and Deuterons
106(8)
4.5.1 Proton-Alpha Particle (p,α) Reactions
108(1)
4.5.2 Proton-Neutron (p,n) Reactions
109(1)
4.5.3 Proton-Gamma (p,gamma;) Reactions
110(1)
4.5.4 Proton-Deuteron Reactions
110(1)
4.5.5 Deuteron-Alpha (d,α) Reactions
111(1)
4.5.6 Deuteron-Proton (d,p) and Deuteron-Neutron (d,n) Reactions
111(3)
4.6 Neutron Interactions
114(3)
4.6.1 Radiative Capture (n,γ) Reactions
114(1)
4.6.2 Charged Particle Emission (CPE)
115(1)
4.6.3 Neutron-Proton (n,p) Reactions
116(1)
4.6.4 Neutron-Neutron (n,2n) Reactions
116(1)
4.7 Activation Product Calculations
117(9)
4.7.1 Neutron Activation Product Calculations
119(5)
4.7.2 Charged Particles Calculations
124(2)
4.8 Medical Isotope Reactions
126(2)
4.9 Transuranium Elements
128(2)
4.10 Photon Interactions
130(3)
4.10.1 Activation by Photons
130(3)
4.11 Fission and Fusion Reactions
133(5)
4.11.1 Fission
133(1)
4.11.2 Fusion
134(4)
4.12 Summary
138(5)
Other Suggested Sources
139(1)
Problems
Chapter 4
139(4)
5 Nuclear Fission and its Products
143(54)
5.1 Fission Energy
145(2)
5.2 Physics of Sustained Nuclear Fission
147(5)
5.3 Neutron Economy and Reactivity
152(2)
5.4 Nuclear Power Reactors
154(3)
5.4.1 Reactor Design: Basic Systems
155(2)
5.5 Light Water Reactors (LWRs)
157(8)
5.5.1 Pressurized Water Reactor (PWR)
157(2)
5.5.2 Boiling Water Reactor (BWR)
159(2)
5.5.3 Inherent Safety Features of LWRs
161(2)
5.5.4 Decay Heat in Power Reactors
163(1)
5.5.5 Uranium Enrichment
164(1)
5.6 Heavy Water Reactors (HWRs)
165(4)
5.6.1 HWR Safety Systems
168(1)
5.7 Breeder Reactors
169(5)
5.7.1 Liquid Metal Fast Breeder Reactor (LMFBR)
171(3)
5.8 Gas-cooled Reactors
174(2)
5.8.1 High-temperature Gas Reactor (HTGR)
175(1)
5.9 Reactor Radioactivity
176(12)
5.9.1 Fuel Cladding
177(1)
5.9.2 Radioactive Products of Fission
178(4)
5.9.3 Production of Individual Fission Products
182(2)
5.9.4 Fission Products in Spent Fuel
184(1)
5.9.5 Fission Product Poisons
185(3)
5.10 Radioactivity in Reactors
188(5)
5.10.1 Activation Products in Nuclear Reactors
188(3)
5.10.2 Tritium Production in Reactors
191(1)
5.10.3 Low-level Radioactive Waste
192(1)
5.11 Summary
193(4)
Acknowledgments
194(1)
Other Suggested Sources
195(1)
Problems
Chapter 5
195(2)
6 Naturally Occurring Radiation and Radioactivity
197(48)
6.1 Discovery and Interpretation
197(2)
6.2 Background Radiation
199(1)
6.3 Cosmic Radiation
200(3)
6.4 Cosmogenic Radionuclides
203(4)
6.5 Naturally Radioactive Series
207(7)
6.5.1 Neptunium Series Radionuclides
214(1)
6.6 Singly Occurring Primordial Radionuclides
214(2)
6.7 Radioactive Ores and Byproducts
216(8)
6.7.1 Resource Recovery
218(1)
6.7.2 Uranium Ores
218(1)
6.7.3 Water Treatment Sludge
219(1)
6.7.4 Phosphate Industry Wastes
219(1)
6.7.5 Elemental Phosphorus
220(1)
6.7.6 Manhattan Project Wastes
221(2)
6.7.7 Thorium Ores
223(1)
6.8 Radioactivity Dating
224(4)
6.8.1 Carbon Dating
224(1)
6.8.2 Dating by Primordial Radionuclides
225(1)
6.8.3 Potassium-Argon Dating
226(1)
6.8.4 Ionium (230Th) Method
227(1)
6.8.5 Lead-210 Dating
227(1)
6.9 Radon and its Progeny
228(12)
6.9.1 Radon Subseries
229(3)
6.9.2 Working Level for Radon Progeny
232(4)
6.9.3 Measurement of Radon
236(4)
6.10 Summary
240(5)
Acknowledgements
241(1)
Other Suggested Sources
241(1)
Problems
Chapter 6
242(3)
7 Interactions of Radiation with Matter
245(62)
7.1 Radiation Dose and Units
245(4)
7.1.1 Radiation Absorbed Dose
246(1)
7.1.2 Radiation Dose Equivalent
246(1)
7.1.3 Radiation Exposure
247(2)
7.2 Radiation Dose Calculations
249(1)
7.2.1 Inverse Square Law
249(1)
7.3 Interaction Processes
250(2)
7.4 Interactions of Alpha Particles and Heavy Nuclei
252(5)
7.4.1 Recoil Nuclei and Fission Fragments
254(1)
7.4.2 Range of Alpha Particles
254(3)
7.5 Beta Particle Interactions and Dose
257(13)
7.5.1 Energy Loss by Ionization
258(1)
7.5.2 Energy Losses by Bremsstrahlung
258(1)
7.5.3 Cerenkov Radiation
259(2)
7.5.4 Attenuation of Beta Particles
261(1)
7.5.5 Range Versus Energy of Beta Particles
262(2)
7.5.6 Radiation Dose from Beta Particles
264(3)
7.5.7 Beta Dose from Contaminated Surfaces
267(1)
7.5.8 Beta Contamination on Skin or Clothing
268(1)
7.5.9 Beta Dose from Hot Particles
269(1)
7.6 Photon Interactions
270(7)
7.6.1 Photoelectric Interactions
271(1)
7.6.2 Compton Interactions
272(2)
7.6.3 Pair Production
274(2)
7.6.4 Photodisintegration
276(1)
7.7 Photon Attenuation and Absorption
277(11)
7.7.1 Attenuation (μ) and Energy Absorption (μEn) Coefficients
280(4)
7.7.2 Effect of E and Z on Photon Attenuation/Absorption
284(2)
7.7.3 Absorption Edges
286(2)
Checkpoints
288(1)
7.8 Energy Transfer and Absorption by Photons
288(8)
7.8.1 Electronic Equilibrium
293(2)
7.8.2 Bragg-Gray Theory
295(1)
7.9 Exposure/Dose Calculations
296(7)
7.9.1 Point Sources
297(1)
7.9.2 Gamma Ray Constant, Γ
298(2)
7.9.3 Exposure and Absorbed Dose
300(1)
7.9.4 Exposure, Kerma, and Absorbed Dose
301(2)
7.10 Summary
303(4)
Acknowledgments
303(1)
Other Suggested Sources
304(1)
Problems
Chapter 7
304(3)
8 Radiation Shielding
307(58)
8.1 Shielding of Alpha-Emitting Sources
307(1)
8.2 Shielding of Beta-Emitting Sources
308(6)
8.2.1 Attenuation of Beta Particles
308(3)
8.2.2 Bremsstrahlung Effects for Beta Shielding
311(3)
8.3 Shielding of Photon Sources
314(24)
8.3.1 Shielding of Good Geometry Photon Sources
315(7)
8.3.2 Half-Value and Tenth-Value Layers
322(2)
8.3.3 Shielding of Poor Geometry Photon Sources
324(6)
8.3.4 Use of Buildup Factors
330(1)
8.3.5 Effect of Buildup on Shield Thickness
331(2)
8.3.6 Mathematical Formulations of the Buildup Factor
333(5)
8.4 Gamma Flux for Distributed Sources
338(19)
8.4.1 Line Sources
339(2)
8.4.2 Ring Sources
341(1)
8.4.3 Disc and Planar Sources
342(1)
8.4.4 Shield Designs for Area Sources
343(7)
8.4.5 Gamma Exposure from Thick Slabs
350(5)
8.4.6 Volume Sources
355(1)
8.4.7 Buildup Factors for Layered Absorbers
356(1)
8.5 Shielding of Protons and Light Ions
357(3)
8.6 Summary
360(5)
Acknowledgments
360(1)
Other Suggested Sources
361(1)
Problems
Chapter 8
361(4)
9 Internal Radiation Dose
365(50)
9.1 Absorbed Dose in Tissue
365(1)
9.2 Accumulated Dose
366(4)
9.2.1 Internal Dose: Medical Uses
369(1)
Checkpoints
369(1)
9.3 Factors In The Internal Dose Equation
370(13)
9.3.1 The Dose Reciprocity Theorem
377(1)
9.3.2 Deposition and Clearance Data
378(1)
9.3.3 Multicompartment Retention
378(5)
9.4 Radiation Dose from Radionuclide Intakes
383(22)
9.4.1 Risk-Based Radiation Standards
384(1)
9.4.2 Committed Effective Dose Equivalent (CEDE)
385(1)
9.4.3 Biokinetic Models: Risk-Based Internal Dosimetry
386(2)
9.4.4 Radiation Doses Due to Inhaled Radionuclides
388(10)
9.4.5 Radiation Doses Due to Ingested Radionuclides
398(7)
9.5 Operational Determinations of Internal Dose
405(3)
9.5.1 Submersion Dose
406(1)
Checkpoints
406(2)
9.6 Tritium: a Special Case
408(3)
9.6.1 Bioassay of Tritium: a Special Case
410(1)
9.7 Summary
411(4)
Other Suggested Sources
412(1)
Problems
Chapter 9
412(3)
10 Environmental Dispersion
415(40)
10.1 Atmospheric Dispersion
417(12)
10.1.1 Atmospheric Stability Effects on Dispersion
420(2)
10.1.2 Atmospheric Stability Classes
422(2)
10.1.3 Calculational Procedure: Uniform Stability Conditions
424(2)
10.1.4 Distance xmax of Maximum Concentration (Χmax)
426(1)
10.1.5 Stack Effects
427(2)
Checkpoints
429(1)
10.2 Nonuniform turbulence: Fumigation, Building Effects
429(9)
10.2.1 Fumigation
429(2)
10.2.2 Dispersion for an Elevated Receptor
431(1)
10.2.3 Building Wake Effects: Mechanical Turbulence
432(1)
10.2.4 Concentrations of Effluents in Building Wakes
433(2)
10.2.5 Ground-level Area Sources
435(1)
10.2.6 Effect of Mechanical Turbulence on Far-field Diffusion
436(2)
10.3 Puff Releases
438(1)
10.4 Sector-Averaged Χ/Q Values
439(4)
10.5 Deposition/Depletion: Guassian Plumes
443(9)
10.5.1 Dry Deposition
443(4)
10.5.2 Air Concentration Due to Resuspension
447(2)
10.5.3 Wet Deposition
449(3)
10.6 Summary
452(3)
Other Suggested Sources
452(1)
Problems
Chapter 10
453(2)
11 Nuclear Criticality
455(34)
11.1 Nuclear Reactors and Criticality
456(8)
11.1.1 Three Mile Island Accident
456(2)
11.1.2 Chernobyl Accident
458(3)
11.1.3 NRX Reactor: Chalk River, Ontario, December 1952
461(1)
11.1.4 SL-1 Accident
461(1)
11.1.5 K-reactor, Savannah River Site, 1988
462(1)
11.1.6 Fukushima-Daichi Plant---Japan, March 11, 2011
463(1)
11.2 Nuclear Explosions
464(6)
11.2.1 Fission Weapons
464(1)
11.2.2 Fusion Weapons
465(1)
11.2.3 Products of Nuclear Explosions
466(1)
11.2.4 Fission Product Activity and Exposure
467(2)
Checkpoints
469(1)
11.3 Criticality Accidents
470(5)
11.3.1 Y-12 Plant, Oak Ridge National Laboratory, TN: June 16, 1958
470(1)
11.3.2 Los Alamos Scientific Laboratory, NM: December 30, 1958
471(1)
11.3.3 Idaho Chemical Processing Plant: October 16, 1959, January 25, 1961, and October 17, 1978
472(1)
11.3.4 Hanford Recuplex Plant: April 7, 1962
473(1)
11.3.5 Wood River Junction RI: July 24, 1964
473(1)
11.3.6 UKAEA Windscale Works, UK: August 24, 1970
474(1)
11.3.7 Bare and Reflected Metal Assemblies
474(1)
11.4 Radiation Exposures in Criticality Events
475(1)
11.5 Criticality Safety
476(6)
11.5.1 Criticality Safety Parameters
478(4)
11.6 Fission Product Release in Criticality Events
482(3)
11.6.1 Fast Fission in Criticality Events
483(2)
11.7 Summary
485(4)
Acknowledgments
486(1)
Other Suggested Sources
486(1)
Problems
Chapter 11
486(3)
12 Radiation Detection and Measurement
489(34)
12.1 Gas-Filled Detectors
489(4)
12.2 Crystalline Detectors/Spectrometers
493(1)
12.3 Semiconducting Detectors
494(1)
12.4 Gamma Spectroscopy
495(9)
12.4.1 Gamma-Ray Spectra: hv ≤ 1.022 MeV
495(5)
12.4.2 Gamma-Ray Spectra: hv ≥ 1.022 MeV
500(2)
12.4.3 Escape Peaks and Sum Peaks
502(1)
12.4.4 Gamma Spectroscopy of Positron Emitters
503(1)
12.5 Portable Field Instruments
504(5)
12.5.1 Geiger Counters
504(1)
12.5.2 Ion Chambers
505(1)
12.5.3 Microrem Meters
506(1)
12.5.4 Alpha Radiation Monitoring
506(1)
12.5.5 Beta Radiation Surveys
507(1)
12.5.6 Removable Radioactive Surface Contamination
508(1)
12.5.7 Instrument Calibration
509(1)
12.6 Personnel Dosimeters
509(2)
12.6.1 Film Badges
509(1)
12.6.2 Thermoluminescence Dosimeters (TLDs)
510(1)
12.6.3 Pocket Dosimeters
511(1)
12.7 Laboratory Instruments
511(12)
12.7.1 Liquid Scintillation Analysis
511(4)
12.7.2 Proportional Counters
515(2)
12.7.3 End-window GM Counters
517(1)
12.7.4 Surface Barrier Detectors
518(1)
12.7.5 Range Versus Energy of Beta Particles
519(1)
Other Suggested Sources
520(1)
Problems
Chapter 12
521(2)
13 Statistics in Radiation Physics
523(48)
13.1 Nature of Counting Distributions
523(11)
13.1.1 Binomial Distribution
525(1)
13.1.2 Poisson Distribution
525(2)
13.1.3 Normal Distribution
527(3)
13.1.4 Mean and Standard Deviation of a Set of Measurements
530(1)
13.1.5 Uncertainty in the Activity of a Radioactive Source
531(2)
13.1.6 Uncertainty in a Single Measurement
533(1)
Checkpoints
533(1)
13.2 Propagation of Error
534(4)
13.2.1 Statistical Subtraction of a Background Count or Count Rate
535(2)
13.2.2 Error Propagation of Several Uncertain Parameters
537(1)
13.3 Comparison of Data Sets
538(3)
13.3.1 Are Two Measurements Different?
538(3)
13.4 Statistics for the Counting Laboratory
541(10)
13.4.1 Uncertainty of a Radioactivity Measurement
541(1)
13.4.2 Determining a Count Time
542(2)
13.4.3 Efficient Distribution of Counting Time
544(1)
13.4.4 Detection and Uncertainty for Gamma Spectroscopy
545(2)
13.4.5 Testing the Distribution of a Series of Counts (the Chi-square Statistic)
547(1)
13.4.6 Weighted Sample Mean
548(1)
13.4.7 Rejection of Data
549(2)
13.5 Levels of Detection
551(7)
13.5.1 Critical Level
552(2)
13.5.2 Detection Limit (Ld) or Lower Level of Detection (LLD)
554(4)
13.6 Minimum Detectable Concentration or Contamination
558(4)
13.6.1 Minimum Detectable Concentration (MDConc.)
558(2)
13.6.2 Minimum Detectable Contamination (MDCont.)
560(1)
13.6.3 Less-than Level (Lt)
561(1)
13.6.4 Interpretations and Restrictions
561(1)
13.7 Log Normal Data Distributions
562(9)
13.7.1 Particle Size Analysis
565(4)
Acknowledgment
569(1)
Other Suggested Sources
569(1)
Chapter 13 - Problems
569(2)
14 Neutrons
571(36)
14.1 Neutron Sources
571(2)
14.2 Neutron Parameters
573(2)
14.3 Neutron Interactions
575(3)
14.3.1 Neutron Attenuation and Absorption
576(2)
14.4 Neutron Dosimetry
578(13)
14.4.1 Dosimetry for Fast Neutrons
581(2)
14.4.2 Dose from Thermal Neutrons
583(2)
14.4.3 Monte Carlo Calculations of Neutron Dose
585(3)
14.4.4 Kerma for Neutrons
588(1)
14.4.5 Dose Equivalent Versus Neutron Flux
588(3)
14.4.6 Boron Neutron Capture Therapy (BNCT)
591(1)
14.5 Neutron Shielding
591(7)
14.5.1 Neutron Shielding Materials
591(2)
14.5.2 Neutron Shielding Calculations
593(1)
14.5.3 Neutron Removal Coefficients
594(3)
14.5.4 Neutron Attenuation in Concrete
597(1)
14.6 Neutron Detection
598(7)
14.6.1 Measurement of Thermal Neutrons
599(1)
14.6.2 Measurement of Intermediate and Fast Neutrons
600(2)
14.6.3 Neutron Foils
602(2)
14.6.4 Albedo Dosimeters
604(1)
14.6.5 Flux Depression of Neutrons
604(1)
14.7 Summary
605(2)
Acknowledgment
605(1)
Other Suggested Sources
605(1)
Problems
Chapter 14
606(1)
Answers to Selected Problems 607(6)
Appendix A 613(2)
Appendix B 615(10)
Appendix C 625(4)
Appendix D 629(28)
Index 657
JAMES E. MARTIN, PhD, CHP, is Associate Professor (Emeritus) at the University of Michigan where he has done research and teaching on environmental and public health aspects of radiation with an emphasis on radiation physics since 1982. He also served 25 years (1957-81) with the U.S. Public Health Service and Environmental Protection Agency, doing environmental assessments of radioactive materials including protection standards. His doctorate is in Radiological Health. Professor Martin is certified in Health Physics by the American Board of Health Physics and has published over 40 peer-reviewed papers and numerous articles and reports. Advisory Committee memberships include two National Academy of Science committees, the Science Advisory Board of the Environmental Protection Agency, and the U.S. Department of Energy.
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