Applied Modeling and Computations in Nuclear ... - ACS Publications

Subject Index

Downloaded by 80.82.77.83 on April 24, 2018 | https://pubs.acs.org Publication Date: November 16, 2006 | doi: 10.1021/bk-2007-0945.ix002

3

A M C N P code system, description, 168-170 Accelerator facilities, airborne releases, radioactive substances, effective dose to public, 104-114 Activated charcoal devices, count data, 264-265/; 268/ Adaptive differencing strategy in P E N T R A N code system, 168 Adult male whole-body model. See VIP-Man Africa. See Gabon Afterpulse probability in NIST system, 37-38 Air density effect on coefficients of dispersion, 263-264/ A i r monitoring program efficiency analysis at KhmePnits'kiy nuclear power plant, 298, 300-304 A i r pathway risks, radionuclides and chemicals released during Cerro Grande Fire, 84-85 Air transport pathway, radionuclides and chemicals released during Cerro Grande Fire, 76/ 77-79 Alarm algorithm testing for radiation portal monitor systems, 204 Alpha particles in scintillation cells, counting efficiencies, 257-264/ American Society for Testing and Materials (ASTM) interlaboratory standards, 20 Angular distribution, cosmic-ray protons, 213-214/ Applications air monitoring efficiency, KhmePnits'kiy nuclear power plant, 298, 300-304

computed tomography, 172-174/ decay from long-lived radionuclide, counting using Bayesian inference, 352-353 homeland security, models of radiation portal monitors, 195206 radiation dose to space crews, solar wind influence on cosmic-ray intensity, 208 spent fuel cask for spent nuclear fuel storage, flux/dose determination, 177-180 waste assay, prompt gamma neutron activation analysis, 170-172/ Applications, Monte Carlo N-particle transport code extension, 187-192 Arbitrary function, parameter estimation, 324-325 Argonne National Laboratory, R E S R A D codes, 59 Assessing risk and modeling radionuclide transport, R E S R A D family of codes, 58-70 A S T M . See American Society for Testing and Materials Asymptote, background, Poisson detection decisions and detection limits, 29-30 Asymptote, extreme low-level Poisson detection decisions and limits for paired counting, 30-33 Asymptotic counting uncertainties, counting in real-time mode, 224 Automated Adjoint Accelerated M C N P . See A M C N P code system, description Average blank count, method to compensate for uncertainty in blank count, 307-308 3

361

Semkow et al.; Applied Modeling and Computations in Nuclear Science ACS Symposium Series; American Chemical Society: Washington, DC, 2006.

362 Average decision levels in average upper bounds for errors of both types, 310-311/ Average detection limits in average upper bounds for errors of both types, 311-313 Average upper bounds for errors of both types, compensation for uncertainty in blank count, 309-313


Β 133

B a check source testing, 204-205/ 206/ Background asymptote, Poisson detection decisions and detection limits, 29-30 counts, Poisson hypothesis validity, 21/33-38 radiation, importance in future nuclear science research, 7-8 signal value, estimates, 301 See also Blank Barometric pressure, source, nonPoisson, non-random C-background variance, 36 Baseline. See Background; Blank Bayes theorem and prior distributions, 340-342 Bayesian approach to internal dosimetry, 94-96 Bayesian inference for binomial and Poisson distributions, 335-356 Bayesian inference from binomial distribution, cases Ν known, ρ unknown, 343-344 Ν unknown, ρ known, 344-347 Ν, ρ unknown, 347-351 Bayesian inference from Poisson distributions, 351-353 Beta-binomial (negative hypergeometric) distribution, 338

Beta-decay for mass numbers 90 and 137,152-153 Binomial distribution, Bayesian inference, cases Ν known,/? unknown, 343-344 Ν unknown, ρ known, 344-347 Ν, ρ unknown, 347-351 Binomial distribution, likelihood function, 337 Binomial distribution, principles, 336 Binomial probability parameter, 338 Biota Dosimetry Working Group, 66 Blank nuclear detection, 19-41 uncertainty, decision levels and detection limits in paired counting, 305-315 See also Background Boltzmann equation. See Linear Boltzmann equation

Calibration coefficients, γspectrometry measurements, evaluation, 298, 300 C A L P U F F , three-dimensional complex terrain model system, 77 Cargo and vehicle models, numerical modeling, radiation portal monitor systems, 197, 199 Cargo Truck lane model, numerical modeling, radiation portal monitor systems, 197, 199/200-201/ Carroll and Lombard, example, Bayesian estimates, 350, 351 C E D E (Committed Effective Dose Equivalent) calculations at Los Alamos, method comparisons, 9 3 103 Cell type influence on counting efficiencies, alpha particles in scintillation cell, 257-264/



363 Central moment analysis, time interval spectra, versus unbiased fit, 316334 Cerro Grande fire at Los Alamos, modeling exposure, health risk and communication with public, 7 1 92 Chemicals and radionuclides, releases into air and surface water from Cerro Grande fire, geographic area, 72-73/ Chernobyl, Ukraine, 26 April 1986 event, 24,301 Chromatography columns, elution curve simulation, 269-279 Chromatography theories, 269-271 C I N D A (Computer Index to Nuclear Reaction Data), description, 11 Coefficient of dispersion. See J factor Coefficient of variation components, evaluation, 300-301 Coincidence/anticoincidence capability, 186-187 Colorado Springs, Colorado, radon decay measurements in scintillation cells, 258-259,260-264/ Committed Effective Dose Equivalent. See C E D E Comparative detection capabilities in extreme low-level Poisson detection decisions, 33 Complete decay probabilities, radionuclides, 53-54 Compton suppression spectrometer, model, 190-192/ Computational models, human body for radiation protection dosimetry, 115-130 Computed tomography, application, 172-174/ Computer cluster, Lambda, at Los Alamos, for internal dosimetry calculations, 96 Computer Index to Nuclear Reaction Data. See CINDA

Conjugate prior distributions, description, 340, 341-342 Consistent Adjoint Driven Importance Sampling methodology, 168-169 Consortium of Computational Human Phantoms, 124 Constant function parameter estimation, 320-324 Constant rate coefficient, necessary condition in exponential decay, 46 Convergence conditions for Monte Carlo integral, 110 Conversion coefficients for external exposure, 108 Correlated counts in radon measurements, overdispersion corrections, 249-268 Correlation coefficient between workstation and supercomputer internal dosimetry, 97 Correlation coefficient for internal dosimetry and unfolding codes at Los Alamos, 101-102 Cosmic ray propagation, 3dimensional adjoint random-walk calculation, 207-216 Cosmic-ray proton leakage flux, 214— 215/ Cosmic-ray protons, angular distribution, 213-214/ Cosmic-ray spectra, calculations in ecliptic plane, 212 Cosmic rays, definition, 208 Count loss, types, 219-221 Count rate estimation, Poisson process, 316-334 Count scatter in loss-free counting, 229 Counting efficiencies, alpha particles in scintillation cell, 257-262 Counting in live-time mode, 223 Counting in real-time mode, 224-228/ Counting statistics dead time and pile-up, 218-233 overdispersion, 230-232, 338-340


364 stretching the Poisson-normal approximation, 24-29 Critical level. See Decision threshold Critical region in extreme low-level Poisson detection decisions, 31 Critical Value. See Detection Decision Currie's approach, 26, 295-297, 306

D

Detector models, radiation portal monitor systems, 197 Deterministic methods compared to statistical Monte Carlo methods, applications, 170-180 See also Discrete ordinate method Diffusion coefficient, 208-209 Digital coincidence counting for radioisotope standardization, 234236 Discrete ordinates method (S ) applied to Boltzmann particle transport, 164-165, 167 See also Deterministic methods Distribution coefficient. See Partition coefficient Dose assessment for flora and fauna, 65-69 Dose assessment for humans, 63-65 Dose build-up factors, 107 Dose conversion coefficients (DCCs), 66, 67, 68/ Dose conversion factors (DCFs), 64, 111-113/ Draper and Guttman examples, Bayesian estimates, 345, 347, 349 Ducks, dose conversion coefficients, 67, 68/ Dynamic link library, raw data simulation routine, radionuclide standardization, 234-248


N

Dayton, Ohio, radon decay measurements in scintillation cells, 258-259,260-264/ DCCs. See Dose conversion coefficients DCFs. See Dose conversion factors Dead time correction in particle counting, 330 Decay constants for radionuclides in radon decay series, 256-257/ Decaying state, quantum theory, 4 7 48 Decision level, definition, 306 Decision threshold, algebraic expression, 297 Deposition exponent, radionuclides in Trinitite, 153-154/ Detection capabilities, concepts and international standards, 20-22 Detection decision, algebraic expression, 20-22 Detection limit algebraic expression, 20-22 Currie's, 297 determination, 306-307 evaluation for environmental monitoring techniques, 293-304 extreme low-level Poisson detection decisions, 32 Detection limit ratio, background signal function, 298, 299/ Detection system response, coincidence/anticoincidence modes, 186-187

Ε-Van model, realistic radiation transport models, 197 Effective dose equivalent. See Effective dose Effective dose radionuclides, 63-64, 112-113 Elution curve peaks, shape dependence on number of theoretical plates, 274-276/



365 Elution curve simulation for External exposure, humans chromatography columns, 269radioactive plume, dose kernel 279 integration, 105-109 Emissions Production Model, 78 radionuclides present in the E M P I R E (Nuclear Reaction Model environment, 65 Code), description, 13, 15/ Extrapolation fit parameters for beta Empirical distributions and tests, and gamma input, digital Poisson background hypothesis, 3 5 coincidence counting software, 38 243-245 E N D F (Evaluated Nuclear Data File) database, description, 11, 13, 14/ E N S D F (Evaluated Nuclear Structure F Data File), 13, 16-17/ 184-185 Environmental monitoring techniques, Fauna and flora, dose assessment, 6 5 67, 68/ detection limit evaluation, 293304 Federal Guidance Reports (US), 64 Fermi, Enrico, 145 Environmental risk analysis. See Risk Fermi Golden Rule No. 2, 48 assessment Field data, radiation portal monitor Environmental risk assessment. See Risk assessment deployments, 196 Euler-Mascheroni constant, 319 Fire at Los Alamos, modeling Evaluated Nuclear Data File. See exposure, health risk and ENDF communication with public, 7 1 Evaluated Nuclear Structure Data File. 92 See ENSDF Fitting alternative, radionuclide halfExplosive yield, Gadget, 150-154, life determinations, 290-291 156/ Flora and fauna, dose assessment, 6 5 Explosives, estimated risk associated 67, 68/ with air release during Cerro Grande Flux/dose determination, spent fuel Fire, 84-85 cask for spent nuclear fuel storage, Exponential decay law 177-180 discovery, 42-44 Ford Econoline van. See Ε-Van model experimental verification, 49-50 Forest fires, combustion product first theory, 44-46 behavior, 77 Exponential decay theory, 44-49 Freeze-out time, Trinitite, 147-148, Exponential directional weighted 156r scheme, 165 Frequentist approach to probability Exponential time interval distribution, interpretation, 342 moment analysis, 325-330 Exposure scenarios, radionuclides and chemicals released during G Cerro Grande Fire, 82-83 External effective dose calculation by Gabon, Africa, natural reactors, Monte Carlo dose kernel thermohydraulic and nuclear integration, 104-114 modeling, 131-141



366 Gadget explosive yield, 150-154, 156/ first nuclear explosive device, 143— 144 Gamma distribution, general model, 338-339 Gauss-Seidel iterative techniques, 134, 165 Gedcke-Hale method, backward counting, 223 Glueckauf equation of chromatography, 271,277-278 Ground zero, desert sand meltdown from Trinity Test, 145 See also Trinitite

High frequency deviations, uncertainties source, 284-285, 286287 Homeland security application, models of radiation portal monitors, 195-206 Human anatomy modeling for radiation dosimetry, 115-130 Human dose assessment, R E S R A D codes, 63-65 Hypothesis testing for detection decisions and capabilities, basic concepts, 20-22

H

I C R M . See International Committee for Radionuclide Metrology ICRP. See International Commission on Radiological Protection Implosion compression factor in Trinity Test, calculations, 155, 156/ Ingestion and inhalation, radiation dose, 64-65 Ingestion pathways, radiation exposure, 62-63 Inhalation pathways, radiation exposure, 60, 62 Instabilities in uncertainty budget, sensitivity, 285 Inter-arrival time distributions, background in NIST system, 36-38 Interdisciplinary nature, risk assessment, overview, 4-5 Internal biota dose calculations 66, 67 Internal dosimetry calculations using Markov chain Monte Carlo, 93-103 International Commission on Radiological Protection (ICRP) bikinetic methods, 94 biota dose evaluation, 65-66 publications on effective dose, 6 3 64

Half-life measurements (radionuclides), uncertainties, 282292 Hanford reactors, 146 Hazard quotient, definition, 75 Hazard quotients, estimated air pathway risks from radionuclides and chemicals released during Cerro Grande Fire, 84-85 Health risk calculations from radionuclides and chemicals release during Cerro Grande Fire, recommendations, 89-90 Health risk communication on radionuclides and chemicals release during Cerro Grande Fire, recommendations, 90-91 Heliospheric transport equation, random-walk solution, 207216 Heterogeneous Windows Cluster, increased speed by parallel processing, 202-203 Hexahydro-1,3,5-trinitro-1,3,5triazine. See R D X



367 International Committee for Radionuclide Metrology (ICRM) Conference on Low-level Radioactivity Measurement Techniques, 20 Radionuclides Techniques Working Group, 236 International Organization for Standardization (ISO), recommendations for detection and quantification, 20 International Union of Pure and Applied Chemistry (IUPAC), recommendations for detection and quantification, 20 ISO. See International Organization for Standardization I U P A C . See International Union of Pure and Applied Chemistry

J factor (coefficient of dispersion) activated charcoal devices, 265, 268/ calculations, 251-257 liquid scintillation charcoal devices, 265-268/ scintillation cells, 262-264/ Jaynes, prior distributions, 340-341, 350-351 Jeffreys, prior distributions, 340, 341, 346, 348

Κ K . See Partition coefficient Khmel'nits'kiy nuclear power plant, Ukraine, air monitoring program, 298-304 K r case study, blank as environmental baseline, 2 1 / 22-24 d

8 5

L Lambda computer cluster, Los Alamos, internal dosimetry calculations, 96 Laplace prior distribution, 340 Large-scale simulation system, radiation portal monitor configurations, 196-197, 198/ Leakage flux, cosmic-ray proton, 214— 215/ Least-squares fit, exponential decay curve, uncertainty problems, 282292 Least squares fitting exponential function to time interval distribution, 331 'unbiased' method, 331-332, 333/ * Likelihood functions for multiple sampling, 337 Linear Boltzmann equation, 163164 Linear diamond-differencing scheme, 165 Liquid scintillation charcoal devices, count data, 265-267, 268/ Live-time mode counting, 223 Los Alamos National Laboratory, New Mexico, Cerro Grande fire, modeling exposure, health risk and communication with public, 7 1 92 Loss correction factor variance in lossfree counting, 229 Loss corrections, counting in real-time mode, 224-227 Loss-free counting, 228-230 Low frequency deviations accounting for, 288-290 uncertainties source, 285 Lucas cell (alpha scintillation cell), J factor, 251,257 See also Scintillation cells


368


M MacLaurin series expansion, 243 Markov chain, definition, 95 Markov chain Monte Carlo method for internal dosimetry calculations, 93-103 See also Stochastic Markov approach M A R L A P . See Multi-Agency Radiological Laboratory Analytical Protocols Manual Maximum likelihood estimation method, 331-332, 333/ Maximum likelihood estimation statistic, 321-322 Maximum likelihood estimators, binomial and Poisson distributions, 337 M D A . See Minimum detectable activity Medical imaging diagnosis, computed tomography application, 172-174/ Medium frequency deviations, identification and treatment, 287288 Medium frequency deviations, uncertainties source, examples, 285 Mercury determination in waste, prompt gamma neutron activation analysis, 170-172/ MighelPs least square, 331 Minimum detectable activity (MDA), definition, 294-295 Minimum detectable activity ( M D A ) for nuclear power plant emission control, 301-303/ Minimum Detectable Value. See Detection Limit Minimum Quantifiable Value. See Quantification Limit M I R D Phantom, heterogeneous anthropomorphic model, 116118/

Modeling radionuclide transport and assessing risk, R E S R A D family of codes, 58-70 Molecular dynamic theory of chromatography, 269-270 Moment analysis, exponential time interval distribution, 325-330 Monte Carlo dose kernel integration, external effective dose, calculation, 104-114 Monte Carlo methods compared to deterministic methods, real-world applications, 170-180 Monte Carlo methods computational models in radiation dosimetry, 119120 Monte Carlo methods for particle transport simulation, 166, 167 Monte Carlo N-particle transport code extension, 183-194 Multi-Agency Radiological Laboratory Analytical Protocols Manual ( M A R L A P ) , 20, 26

Ν National Incident Management System implementation, 90-91 National Institute for Science and Technology study on background counts, 2 1 / 3 5 - 3 9 National Library of Medicine, Visible Human Project, images, 120-122 National Nuclear Data Center (NNDC), 10-18 See also entity names; US EPA Natural fission reactors, thermohydraulic and nuclear modeling, 131-141 Negative-binomial and Poisson Ν prior distributions for multiple sampling, 344-346 Neutron fluences in Trinity Test, 148— 150



369 New Mexico. See Los Alamos National Laboratory; Trinity Test Neyman-Pearson confidence intervals, 307 Neyman's chi square, 320, 322, 331 N N D C . See National Nuclear Data Center Non-counting variance, 24 Non-extending dead-time count loss, definition, 219-220 exponential time interval distribution, moment analysis, 327-330 Noninformative Ν prior distributions for multiple sampling, 346-347 Noninformative prior distributions, description, 340-341 N S R (Nuclear Science References) database, description, 11 Nuclear counting statistics, overview of progress, 218-233 Nuclear eyeball size in Trinity Test, 155, 156/ Nuclear installation areas, detection limit evaluations, environmental monitoring techniques, 293304 Nuclear Reaction Model Code. See EMPIRE Nuclear science and risk assessment, connection, 3-7 Nuclear science example using Bayesian inference, 352-353 Nuclear Science References database. See N S R database Nuclear science research, risk assessment guide, 7-8 Nuclear statistics, exponential decay law, 42-56 Nuclear Structure References database. See NSR database Nuclear Wallet Cards, 17-18 NuDat database, 16-17/

Ο Ohio. See Dayton, Ohio Oklo natural reactors, thermohydraulic and nuclear modeling, 131-141 Oklo two-dimensional numerical reactor model development, 135138 Operating Characteristic, detection significance test, 22 Operational periodicity in Oklo code predictions, 139-140 Overdispersion corrections due to correlated counts in radon measurements, 249-268 Overdispersion in counting statistics, 230-232, 338-340

Ρ 4π β-γ coincidence method. See Digital coincidence counting Paired counting decision levels and detection limits, 305-315 limits, and extreme low-level Poisson detection decisions, 3 0 33 Parallel Environment Neutral-particle Transport. See P E N T R A N code system Parameter estimation for arbitrary function, 324-325 Parameter estimation for constant function, 320-324 Particle counting with dead time correction, 330 Particle-flux relationship to phasespace density, 209 Particle transport methods, threedimensional, 162-182 Particulate matter less than 10 micrometers. See PMio


370 Partition coefficient (K ), chromatography column simulations, 270-278 Pathway analysis, for R E S R A D (onsite) code, 59-63 Pathways to population exposure, environmental monitoring for radionuclides, 293-294 Pearson's chi-square, 320-321, 322, 331 P E N T R A N code system, description, 168 Performance prediction, γ- and βspectrometry systems, Monte Carlo N-particle transport code extension, 187-192 Phantom. See M I R D phantom Photon radiation from radioactive gases in airborne plume, 105 Plutonium composition in Trinity Test, 155, 156/ Plutonium production for Gadget fuel, 146-147 PMio (particulate matter less than 10 micrometers) model calibration, 78, 80/-81/ Poisson curve fit, chromatography elution peaks, 274-278 Poisson detection decisions detection limits for background asymptote, 29-30 extreme low-level, 30-33 Poisson distribution Bayesian inference, 351-353 likelihood function, 337 principles, 336 properties, 336 Poisson hypothesis for background counts, validity, 2 1 / 33-38 Poisson Ν and negative-binomial prior distributions for multiple sampling, 344-346 Poisson-normal approximation in counting statistics, 24-29


d

Poisson process, count rate estimation, 316-334 Poisson statistics predicted deviations, 218-233 validity criteria, 250 Poisson treatment, exact, history, 2 9 33 Polyvinyl-toluene detection systems, models, 197,200-202/ Primary proton spectrum, randomwalk solution, 211-212 Prior distributions and Bayes theorem, 340-342 Probabilistic approach, exponential decay theory, 44-47 Prompt gamma neutron activation analysis, waste assay, 170-172/ Prompt neutrons in Trinity Test, 154155, 156/ Pulse and gate signal formation logic, 186-187 Pulse height spectra, simulation model in Visual C , 32-bit dynamic link library, 240-241/ Pulse pile-up, count loss, definition, 220 Pulse shapes, simulation model in Visual C**, 32-bit dynamic link library, 238-240 + +

Q Quantification Limit, algebraic expression, 20-22 Quantum mechanics treatment, radioactive decay, 47-48 Quantum Zeno effect, 48, 50

R Radiation dosimetry, human anatomy modeling, 115-130



371

Radiation portal monitors, models for homeland security applications, 195-206 Radioactive decay, specific nuclides, statistical simulation, Monte Carlo N-particle transport code extension, application, 187-192 Radioactive plume-caused external exposure, dose kernel integration, 105-109 Radioactive plume external effective dose, calculation by Monte Carlo dose kernel integration, 104-114 Radionuclide standardization, raw data simulation by dynamic link library, 234-248 Radionuclides, complete decay probabilities, 53-54 Radionuclides with chemicals, releases into air and surface water from Cerro Grande fire, geographic area, 72-73/ Radon decay series, physical data for radionuclides, 256-257/ Radon measurements, overdispersion corrections due to correlated counts, 249-268 Random-walk solution, heliospheric transport equation, 207-216 R D X (hexahydro-1,3,5-trinitro-1,3,5triazine), risk from air release, Cerro Grande Fire, 84-85 Real-time mode, counting, 224-228/ R E S R A D code family, modeling radionuclide transport and assessing risk, 58-70 availability, 69 R E S R A D - B I O T A code, 60 R E S R A D - B U I L D code, 60 RESRAD-OFFSITE code, 60 R E S R A D (onsite) code, pathway analysis, 59-63 R E S R A D - R E C Y C L E code, 60 Risk assessment application to nuclear science, overview, 3-9

Risk assessment codes, R E S R A D family, 58-70 Risk communication on radionuclides and chemicals release during Cerro Grande Fire, 87, 89-91 Risk equation with components, 4-7 Rutherford and Soddy, exponential decay law discovery, 42-44

Schweidler, first exponential decay theory, 44-46 Scintillation cells, 257-263/ See also Lucas cell Simplification, risk estimation methods, importance to nuclear science research, 8 Simulation model, Visual C""", 32-bit dynamic link library, 236-240,241/ predictions, 240,242-245 testing, 246-247 Single workstation calculations on internal dosimetry at Los Alamos, 96-97 S method. See Discrete ordinates method; Deterministic methods Solar wind, influence on cosmic-ray intensity, radiation dose determination to space crew, 208 Source modeling in extended Monte Carlo N-particle transport code, 184-186 Space crews, radiation dose determination, solar wind influence on cosmic-ray intensity, 208 Standard deviations, counting in real time mode, 224, 226/ 227-28/ Stochastic Markov approach to radioactive decay, 50-53 See also Markov chain Stylized models, human body for radiation protection dosimetry, 1 Ιο ί 18/ 4

N


372


Subjectivist approach to probability interpretation, 342 Surface pathway risks, estimated risk associated with air release during Cerro Grande Fire, 85-86, 88/ Surface water transport, radionuclides and chemicals released during Cerro Grande Fire, 79, 82 Survival functions, digital coincidence counting software, 240,242 Swiss directive HSK-R-41, dose conversion factors, 112, 113/

Τ Temperature profiles, uranium concentrations in Oklo twodimensional numerical reactor model, 136-139 Thallium-doped sodium-iodide-based detection systems, models, 197, 200-202/ Theoretical plates, chromatography elusion curve simulations, 269279 Three-dimensional particle transport methods, 162-182 Throughput factors, definition, 221 Time interval distribution analysis, 317 Time interval distribution central moments, 326/ 331 Time interval distributions between consecutive events, 221-223 Time interval spectra, central moment analysis, versus unbiased fit, 316334 Tomographic model development, human body for radiation protection dosimetry, 117, 119, 120-125 Transient computer model development for Oklo natural reactor, 133-135

Trinitite, radioactivity and freeze-out time, 146-148, 154, 156/ See also Ground zero Trinity Test, modeling the effects, 142-159

U Ukraine. See Chernobyl; KhmePnits'kiy nuclear power plant Unbiased fit versus central moment analysis of time interval spectra, 316-334 Uncertainties in modeling radionuclide and chemical releases from Cerro Grande Fire, 87 Uncertainties in radionuclide half-life measurements, 282-292 Uncertainty component in loss-free counting, 229 Uncertainty components, aggregate, 290 Uncertainty equations, 283-285 Uncertainty estimate improvement, importance to nuclear science research, 8 Uncertainty in blank count, method to compensate, 307-313 Unfolding code calculations for internal dosimetry at Los Alamos, 98-102 Upper bounds for errors, method to compensate for uncertainty in blank count, 308-309 Uranium concentrations with temperature profiles in Oklo twodimensional numerical reactor model, 136-139 US E P A Report 402-R-93-081, dose conversion factors, 111-112, 113/ See also entity names; National entries


373 Visible Photographic Man. See VIPMan


V

Validation and verification, radiation portal monitor systems, 200-203 Validation importance to nuclear science research, 8 Validity criteria for Poisson statistics, 250 Validity for Poisson hypothesis for background counts, 2 1 / 3 3 - 3 8 Variance reduction techniques, Monte Carlo calculations, 166-167 Verification and validation, radiation portal monitor systems, 200-203 VIP-man model construction, 120-124 human anatomy modeling for radiation dosimetry, Î15-130 Visible Human Project, National Library of Medicine, images, 120122

W Washington State. See Hanford reactors Waste assay, prompt gamma neutron activation analysis, 170-172/ Waste determination, flux/dose determination, spent fuel cask for spent nuclear fuel storage, 177— 180 Weighted average, Poisson process, 318-320

Zero dead time counting, 228-230


Applied Modeling and Computations in Nuclear ... - ACS Publications

Recommend Documents