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9781558995161

Scientific Basis for Nuclear Waste Managment Xxiii

by ;
  • ISBN13:

    9781558995161

  • ISBN10:

    1558995161

  • Format: Hardcover
  • Copyright: 2000-11-01
  • Publisher: Materials Research Society
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Summary

This long-standing symposia series has become the premier, international forum for scientific and engineering issues related to all levels and types of radioactive wastes and their management. Topics include: fuel cladding and spent nuclear fuel; container fabrication and corrosion; performance assessment; repository performance; radionuclide sorption and transport; cement-based materials and waste containment; corrosion of ceramic wasteforms; structure and characterization of ceramics; radiation effects; natural analogs; wasteform characterization and processing; and corrosion and characterization of glass wasteforms.

Table of Contents

Preface xix
Materials Research Society Symposium Proceedings xx
FUEL CLADDING AND SPENT NUCLEAR FUEL
Cladding Evaluation in the Yucca Mountain Repository Performance Assessment
3(8)
Eric R. Siegmann
J. Kevin McCoy
Robert Howard
Long-Term Creep Behavior of Spent Fuel Cladding for Storage and Disposal
11(6)
T. Bredel
C. Cappelaere
R. Limon
G. Pinte
P. Bouffioux
Hydride-Related Degradation of Spent-Fuel Cladding Under Repository Conditions
17(6)
H.M. Chung
Analysis of Dry Storage Temperature Limits for Zircaloy-Clad Spent Nuclear Fuel
23(6)
T.A. Hayes
R.S. Rosen
M.E. Kassner
K.S. Vecchio
*Spent Fuel Dissolution: An Examination of the Impacts of Alpha-Radiolysis
29(12)
P.A. Smith
L.H. Johnson
Uranium Oxide Mass Loss Rate in Water for an Interface Under Alpha-Irradiation
41(6)
C. Corberl
J-F. Lucchini
G. Sattonnay
M-F. Barthe
F. Huet
P. Dehaudt
C. Ardois
B. Hickel
J.L. Paul
Potential Incorporation of Transuranics Into Uranium Phases
47(8)
C.W. Kim
D.J. Wronkiewicz
E.C. Buck
In Situ Long-Term Measurements of pH and Redox Potential During Spent Fuel Leaching Under Stationary Conditions---The Method and Some Preliminary Results
55(6)
K. Spahiu
L. Werme
J. Low
U-B. Eklund
SIMFUEL Leaching Experiments in Presence of Gamma External Source (60Co)
61(6)
J.A. Serrano
J. Quinones
P.P. Diaz Arocas
J.L. Rodriguez Almazan
J. Cobos
J.A. Esteban
A. Martinez-Esparza
Oxidative Alteration of Spent Fuel in a Silica-Rich Environment: SEM/AEM Investigation and Geochemical Modeling
67(10)
Yifeng Wang
Huifang Xu
CONTAINER FABRICATION AND CORROSION
*Fabrication and Testing of Copper Canister for Long-Term Isolation of Spent Nuclear Fuel
77(12)
L.O. Werme
Passive Dissolution and Localized Corrosion of Alloy 22 High-Level Waste Container Weldments
89(6)
D.S. Dunn
G.A. Cragnolino
N. Sridhar
Stress Corrosion Crack Growth in Copper for Waster Canister Applications
95(8)
Kjell Pettersson
Magnus Oskarsson
Pitting Corrosion of Copper: Equilibrium-Mass Transport Limitation
103(6)
C. Taxen
Mechanical Properties, Microstructure and Corrosion Performance of C-22 Alloy Aged at 260°C to 800°C
109(6)
R.B. Rebak
T.S.E. Summers
R.M. Carranza
Theoretical Study of Bulk and Surface Properties of Digenite Cu2-δS
115(8)
P.A. Korzhavyi
I.A. Abrikosov
B. Johansson
PERFORMANCE ASSESSMENT
Chemical Interactions in the Near-Field of a Repository for Spent Nuclear Fuel---A Modeling Study
123(6)
Heikki Kumpulainen
Jarmo Lehikoinen
Arto Muurinen
Results of an Aqueous Source Term Model for a Radiological Risk Assessment of the Drigg LLW Site, U.K.
129(6)
J.S. Small
P.N. Humphreys
T.L. Johnstone
R. Plant
M.G. Randall
D.P. Trivedi
Long-Term Performance Assessment for a Proposed High-Level Radioactive Waste Disposal Site at Yucca Mountain---Explanation of the Shape of Release Curves
135(6)
Sitakanta Mohanty
Robert W. Rice
Safety Assessment of Bore-Hole Repositories for Sealed Radiation Sources Disposal
141(6)
M.I. Ojovan
A.V. Guskov
L.B. Prozorov
A.E. Arustamov
P.P. Poluektov
B.B. Serebryakov
Prediction of Waster Package Life for High-Level Radioactive Waste Disposal at Yucca Mountain
147(8)
Osvaldo Pensado
Sitakanta Mohanty
REPOSITORY PERFORMANCE
Behavior of MgO as a CO2 Scavenger at the Waster Isolation Pilot Plant (WIPP), Carlsbad, New Mexico
155(6)
J.L. Krumhansl
H.W. Papenguth
P-C. Zhang
J.W. Kelly
H.L. Anderson
J.O.E. Hardesty
Vadose Zone Monitoring System for Site Characterization and Transport Modeling
161(6)
J.B. Sisson
A.L. Schafer
J.M. Hubbell
Thermal Parametric Studies for Radioactive Waste Management
167(6)
D. Manzoni
S. Le Bonhomme
B. Soulier
Y. Guilloux
Long-Term Test of Buffer Material at ASPO Hard Rock Laboratory Sweden
173(6)
O. Karnland
Torbjorn Sanden
O2 Consumption in a Granitic Environment
179(6)
I. Puigdomenech
L. Trotignon
S. Kotelnikova
K. Pedersen
L. Griffault
V. Michaud
J-E. Lartigue
K. Hama
H. Yoshida
J.M. West
K. Bateman
A.E. Milodowski
S.A. Banwart
J. Rivas Perez
E-L. Tullborg
Numerical Simulation of Bentonite Extrusion Through a Narrow Planar Space
185(6)
Joonhong Ahn
Paul L. Chambre
Jerome Verbeke
Impact of Porosity Heterogeneity in the Diffusion of Some Alkali-and alkaline Earth-Metals in Crystalline Rock
191(8)
H. Johansson
J. Byegard
M. Skalberg
RADIONUCLIDE SORPTION AND TRANSPORT
*Simulation of Radionuclide Migration in Groundwater Away From an Underground Nuclear Test
199(12)
A.F.B. Tompson
C.J. Bruton
W.L. Bourcier
D.E. Shumaker
A.B. Kersting
D.K. Smith
S.F. Carle
G.A. Pawloski
J.A. Rard
Assessing the Effective Reactive Surface Area in heterogeneous Media Through the Use of conservative and Reactive Tracers
211(6)
Robert W. Smith
Jonathan R. Ferris
Decay-Series Disequilibrium Study of In Situ Long-Term Radionuclide Transport in Water-Rock Systems
217(8)
Shagde Luo
Teh-Lung Ku
Robert Roback
Micheal Murrell
Travis L. McLing
Chemical Evolution of Leaked High-Level Liquid Wasts in Hanford Soils
225(6)
M. Nyman
J.L. Krumhansl
P. Zhang
H. Anderson
T.M. Nenoff
Technetium-99 Chemistry in Reducing Groundwaters: Implications for the Performance of a Proposed High-Level Nuclear Waste Repository at Yucca Mountain, Nevada
231(6)
Roberto T. Pabalan
David R. Turner
Michael P. Miklas, Jr.
Thermodynamic Interpretations of Chemical Analyses of Unsaturated Zone Water From Yucca Mountain, Nevada
237(6)
Lauren Browning
William M. Murphy
Bret W. Leslie
William L. Dam
Research Into Effects of Repository Heterogeneity
243(6)
M.M. Askarieh
A.V. Chambers
L.J. Gould
Sorption of Uranium and Plutonium on Bentonite Altered by Highly Alkaline Water
249(6)
M. Brownsword
M. Mihara
S.J. Williams
Surface Charge and Electrophoretic Properties of Colloids Obtained From Homoionic and Natural bentonite
255(6)
T. Missana
M.J. Turrero
A. Adell
Diffusion of Plutonium in Compacted Bentonites in the Reducing Condition With Corrosion Products of Iron
261(6)
K. Idemitsu
X. Xia
T. Ichishima
H. Furuya
Y. Inagaki
T. Arima
T. Mitsugashira
M. Hara
Y. Suzuki
Effect of Ionic Charge on Effective Diffusion Coefficient in Compacted Sodium Bentonite
267(8)
H. Sato
Adsorption Parameters for Radioactive Liquid-Waste Migration
275(6)
L.C. Hull
M.N. Pace
G.D. Redden
Effects of Surfactant Modification on the Sorption Behavior of Natural Zeolites for Strontium (2+) and Uranium (6+)
281(6)
James D. Prikryl
F. Paul Bertetti
Roberto T. Pabalan
Experimental Study of the Nickel Solubility in Suphidic Groundwater Under Anoxic Conditions
287(6)
T. Carlsson
U. Vuorinen
T. Kekki
H. Aalto
Effect of Carbonate Concentration on the Sorption of Plutonium Onto Geological Materials
293(6)
G.M.N. Baston
J.A. Berry
M. Brownsword
D.J. Ilett
C.M. Linklater
C.J. Tweed
M. Yui
TEM Investigation of U6+ Re7+ Reduction by Desulfovibrio desulfuricans, a Sulfate-Reducing Bacterium
299(8)
Huifang Xu
Larry L. Barton
Pengchu Zhang
Yifeng Wang
CEMENT-BASED MATERIALS AND WASTE CONTAINMENT
Interaction of Uranium and neptunium With Cementitious Materials Studied by XAFS
307(6)
E.R. Sylwester
P.G. Allen
P. Zhao
B.E. Viani
Prediction of the Long-Term Release of Hazardous Substances From Cement-Based Materials to Water
313(6)
A. Andersson
L.O. Nilsson
Dimensional Analysis of Ionic Transport Mechanisms in Cement-Based Materials
319(6)
R. Barbarulo
J. Marchand
S. Prene
Coupling Between Diffusivity and Cracks in Cement-Based Systems
325(6)
C. Tognazzi
J-M. Torrenti
M. Carcasses
J-P. Ollivier
Clay-Based Grouting Into the EDZ for the Vault Sealing
331(6)
Y. Sugita
T. Fujita
K. Masumoto
N. Chandler
Study on the Effects of Hydraulic Transport of Groundwater in Cement
337(8)
M. Toyohara
M. Kaneko
F. Matsumura
N. Mitsutsuka
Y. Kobayashi
M. Imamura
CORROSION OF CERAMIC WASTEFORMS
Glass/Ceramic Interactions in the Can-in-Canister Configuration for Disposal of Excess Weapons in Plutonium
345(8)
B.P. McGrail
P.F. Martin
H.T. Schaef
C.W. Lindenmeier
A.T. Owen
Aqueous Durability of Titanate Ceramics Designed to Immobilize Excess Plutonium
353(6)
K.P. Hart
Y. Zhang
E. Loi
Z. Aly
M.W.A. Stewart
A. Brownscombe
B.B. Ebbinghaus
W. Bourcier
Composition, Geochemical Alteration, and Alpha-Decay Damage Effects of Natural Brannerite
359(8)
Gregory R. Lumpkin
S.H.F. Leung
M. Colella
Thermodynamic Stability of Actinide Pyrochlore Minerals in Deep Geologic Repository Environments
367(6)
Yifeng Wang
Huifang Xu
Dissolution Kinetics of Titanium Pyrochlore Ceramics at 90°C by Single-Pass Flow-Through Experiments
373(6)
J.P. Icenhower
B.P. McGrail
H.T. Schaef
E.A. Rodriguez
Surface Alteration of Titanate Ceramics in Aqueous Media
379(8)
E.R. Vance
N. Dytlewski
K.E. Prince
K.P. Hart
E. Loi
The Long-Term Corrosion Behavior of Titanate Ceramics for Pu Disposition: Rate-Controlling Processes
387(6)
A.J. Bakel
C.J. Mertz
M.C. Hash
D.B. Chamberlain
Chemical Durability of Yttria-Stabilized Zirconia for Highly Concentrated TRU Wastes
393(8)
Hajime Kinoshita
Ken-ichi Kuramoto
Masayoshi Uno
Shinsuke Yamanaka
Hisayoshi Mitamura
Tsunetaka Banba
STRUCTURE AND CHARACTERIZATION OF CERAMICS
EXAFS and XANES of Plutonium and Cerium Edges From Titanate Ceramics for Fissile Materials Disposal
401(6)
J.A. Fortner
A.J. Kropf
A.J. Bakel
M.C. Hash
S.B. Aase
E.C. Buck
D.B. Chamberlain
Phase Compositions and Elements Partitioning in Two-Phase Hosts for Immobilization of a Rare Earth-Actinide High-Level Waste Fraction
407(6)
S.V. Stefanovsky
S.V. Yudintsev
B.S. Nikonov
A.V. Ochkin
S.V. Chizhevskaya
N.E. Cherniavskaya
A Correlation Between Relative Cation Radius and the Phase Stability of Zirconolite
413(6)
D. Swenson
P. Triyachaoen
Synthesis and Study of 239Pu-Doped Gadolinium-Aluminum Garnet
419(4)
B.E. Burakov
E.E. Anderson
M.V. Zamoryanskaya
M.A. Petrova
Characterization of a Glass-Bonded Ceramic Waste Form Loaded With U and Pu
423(8)
W. Sinkler
T.P. O'Holleran
S.M. Frank
M.K. Richmann
S.G. Johnson
Solid Solubilities of Pu, U, Hf and Gd in Candidate Ceramic Phases for Actinide Waste Immobilization
431(6)
E.R. Vance
M.L. Carter
B.D. Begg
R.A. Day
S.H.F. Leung
Cathodoluminescence of Ce, U and Pu in a Garnet Host Phase
437(6)
M.V. Zamoryanskaya
B.E. Burakov
Al2O3-Doped TiO2 Ceramic Waste Forms Produced by Melting Method
443(6)
Masayoshi Uno
Hajime Kinoshita
Shinsuke Yamanaka
Melting Simulated High-Level Liquid Waste With Addition of TiN and AlN
449(6)
Masayoshi Uno
Hajime Kinoshita
Shinsuke Yamanaka
Isomorphic Capacity of Synthetic Sphene With Respect to Gd and U
455(6)
S.V. Stefanovsky
S.V. Yudintsev
B.S. Nikonov
B.I. Omelianenko
M.I. Lapina
Microstructure and Composition of Synroc Samples Crystallized From a CaCeTi2O7 Chemical System: HRTEM/EELS Investigation
461(8)
Huifang Xu
Yifeng Wang
Robert L. Putnam
Jose Gutierriez
Alexandra Navrotsky
RADIATION EFFECTS
Accelerated Alpha Radiation Damage in a Ceramic Waste Form, Interim Results
469(6)
Steven M. Frank
Stephen G. Johnson
Tanya L. Moschetti
Thomas P. O'Holleran
Wharton Sinkler
David Esh
K. Michael Goff
Formation of Perovskite and Calzirtite During Zirconolite Alteration
475(6)
J. Malmstrom
E. Reusser
R. Giere
G.R. Lumpkin
M.G. Blackford
M. Duggelin
D. Mathys
R. Guggenheim
D. Gunther
Molecular Dynamics Study of the Influence of a Surface on a Simplified Nuclear Glass Structure and on Displacement Cascades
481(6)
A. Abbas
J.M. Delaye
D. Ghaleb
Y. Serruys
G. Calas
Temperature Dependence of Ion Irradiation Induced Amorphization of Zirconolite
487(6)
K.L. Smith
M.G. Blackford
G.R. Lumpkin
N.J. Zaluzec
Radiation and Thermal Effects in Zeolite-NaY
493(6)
Binxi Gu
Lumin Wang
Phil A. Simpson
Leah D. Minc
Rodney C. Ewing
Radiation Effects in Chloride Molten Salt Compositions
499(6)
S.V. Ignatiev
D.V. Pankratov
E.I. Yefimov
Hydrogen Gas Evolution From Water Dispersing Nanoparticles Irradiated With Gamma-Ray
505(6)
S. Seino
R. Fujimoto
T.A. Yamamoto
M. Katsura
S. Okuda
K. Okitsu
R. Oshima
Diamond Detectors for Alpha Monitoring in Corrosive Media for Nuclear Fuel Assembly Reprocessing
511(8)
P. Bergonzo
F. Foulon
A. Brambilla
D. Tromson
C. Mer
B. Guizard
S. Haan
NATURAL ANALOGS
Growth and Alteration of Uranium-Rich Microlite
519(6)
R. Giere
R.J. Swope
E.C. Buck
R. Guggenheim
D. Mathys
E. Reusser
Crandallites and Coffinite: Retardation of Nuclear Reaction Products at the Bangombe Natural Fission Reactor
525(8)
K.A. Jensen
J. Janeczek
R.C. Ewing
P. Stille
F. Gauthier-Lafaye
S. Salah
*Natural Analogs and Performance Assessment for Geologic Disposal of Nuclear Waste
533(12)
William M. Murphy
Using Information From Natural Analogs in Repository Performance Analysis: Examples from Oklo
545(6)
V.M. Oversby
Claystone Constraints on Models of the Long-Term Chemical Evolution of Buffer Porewaters
551(6)
R.C. Arthur
J. Wang
An Archaeological Site at Akrotiri, Greece, as a Natural Analog for Radionuclide Transport: Implications for Validity of Performance Assessments
557(8)
D.L. Hughson
L. Browning
W.M. Murphy
R.T. Green
WASTEFORM CHARACTERIZATION AND PROCESSING
Graphite Processing With Carbon Retention in a Waste Form
565(6)
M.I. Ojovan
O.K. Karlina
V.L. Klimov
G.Yu. Pavlova
Long-Term Behavior of Bitumen Waste Form
571(6)
I.A. Sobolev
A.S. Barinov
M.I. Ojovan
N.V. Ojovan
I.V. Startceva
Z.I. Golubeva
Characterization of a Ceramic Waste Form Encapsulating Radioactive Electrorefiner Salt
577(6)
T.L. Moschetti
W. Sinkler
T. DiSanto
M.H. Noy
A.R. Warren
D. Cummings
S.G. Johnson
K.M. Goff
K.J. Bateman
S.M. Frank
TEM Characterization of Corrosion Products Formed on a Stainless Steel-Zirconium Alloy
583(6)
J.S. Luo
D.P. Abraham
*Leaching Characteristics of the Metal Waste Form From the Electrometallurgical Treatment Process: Product Consistency Testing
589(6)
S.G. Johnson
D.D. Keiser
S.M. Frank
T. DiSanto
A.R. Warren
M. Noy
Behavior of Actinide Ions During Sluge Washing of Alkaline Radioactive Wastes
595(6)
Andrew H. Bond
Kenneth L. Nash
Artem V. Gelis
Mark P. Jensen
James C. Sullivan
Linfeng Rao
Cesium Removal From the Fuel Storage Water at the Savannah River Site R-Building Disassembly Basin Using 3M Empore®-Membrane Filter Technology
601(6)
L.N. Oji
M.C. Thompson
Kurt Peterson
Thomas M. Kafka
Characterization of and Waste Acceptance Radionuclides to be Reported for the Second Macro-Batch of High-Level Waste Sluge Being Vitrified in the DWPF Melter
607(6)
T.L. Fellinger
N.E. Bibler
W.T. Boyce
J.J. Olson
Matrix-Assisted Infrared-Laser Desorption-Ionization Mass Spectrometry of Organic Molecules on NaNO3
613(6)
D.R. Ermer
M. Baltz-Knorr
D. Nakazawa
M.R. Papantonakis
R.F. Haglund, Jr.
Evaluation of Phase- and Element Distribution After Non-Traditional In Situ Vitrification (NTISV) at Los Alamos National Laboratory on a Simulated Adsorption Bed
619(6)
Thomas Hartmann
Concepts for Dry Processing of Spent Nuclear Fuel for Recycling to Light-Water Reactors
625(6)
Jerry Christian
James Sterbentz
David Abbott
K.R. Czerwinski
R. Cacciapouti
Powerful Gels for Power Plant Decontamination
631(6)
D. Cheung
J.L. Pascal
S. Bargues
F. Favier
Development and Testing of a New Porous Crystalline Matrix (Gubka) for Stabilizing Actinide Solutions
637(6)
Albert S. Aloy
A.G. Anshits
A.A. Tretyakov
D.A. Knecht
T.J. Tranter
Y. Macheret
Characterizing Transport and Sorption in Ion-Specific Resin Columns Using Nuclear Magnetic Resonance (NMR) Imaging
643(6)
D.F. Caputo
D.G. Cory
M. Draye
K.R. Czerwinski
Volatilization of Fission Products from Metallic Melts in the Melt-Dilute Treatment Technology Development for Al-Based DOE Spent Nuclear Fuels
649(10)
Thad M. Adams
Andrew J. Duncan
Harold B. Peacock, Jr.
CORROSION AND CHARACTERIZATION OF GLASS WASTEFORMS
The Effect of Adding Crystalline Silicotitanate on the Durability, Liquidus, and Viscosity of Simulated High-Level Waste Glasses at Savannah River Site
659(6)
J.R. Harbour
T.B. Edwards
R.J. Workman
Conductivity-Chemistry Relationship in Simulated Nuclear Waste Glass Melts
665(6)
S.K. Sundaram
Elvis Q. Le
Liquidus Temperature of High-Level Waste Borosilicate Glasses With Spinel Primary Phase
671(6)
Pavel Hrma
John Vienna
Jarrod Crum
Greg Piepel
Martin Mika
Liquidus Temperature of Rare Earth-Alumino-Borosilicate Glasses for Treatment of Americium and Curium
677(6)
Brian J. Riley
John D. Vienna
Michael J. Schweiger
Gadolinium and Hafnium Alumino-Borosilicate Glasses: Gd and Hf Solubilities
683(8)
Donggao Zhao
L.L. Davis
Liyu Li
C.S. Palenik
L.M. Wang
D.M. Strachan
R.C. Ewing
Joint Vitrification of Various Mixed Wastes
691(6)
O.I. Kiryanova
T.N. Lashtchenova
F.A. Lifanov
S.V. Stefanovsky
O.V. Tolstova
Tc-99 and Cs-137 Volatility From the DWPF Production Melter During Vitrification of the First Macrobatch of HLW Sludge at the Savannah River Site
697(6)
N.E. Bibler
T.L. Fellinger
S.L. Marra
R.J. O'Driscoll
J.W. Ray
W.T. Boyce
Americium/Curium Vitrification Process Development Part II
703(6)
Andrew P. Fellinger
Mark A. Baich
Jon W. Duvall
Timothy M. Jones
John E. Marra
Carey B. Miller
Donald H. Miller
David K. Peeler
Theresa K. Snyder
Michael E. Stone
Douglas C. Witt
Liquidus Temperatue and Primary Crystallization Phases in High-Zirconia High-Level Waste Borosilicate Glasses
709(6)
Trevor Plaisted
Pavel Hrma
John Vienna
Antonin Jiricka
Assessment of Nepheline Precipitation in Nuclear Waste Glass Via Thermochemical Modeling
715(6)
T.M. Besmann
K.E. Spear
E.C. Beahm
Characterization and Radiation Resistance of a Mixed-Alkali Borosilicate Glass for High-Level Waste Vitrification
721(6)
J.M. Roderick
D. Holland
C.R. Scales
The Behavior of Silicon and Boron in the Surface of Corroded Nuclear Waste Glasses: An EFTEM Study
727(6)
E.C. Buck
K.L. Smith
M.G. Blackford
Corrosion of Glass-Bonded Sodalite as a Function of pH and Temperature
733(6)
L.R. Morss
M.L. Stanley
C.D. Tatko
W.L. Ebert
Plutonium Silicate Alteration Phases Produced by Aqueous Corrosion of Borosilicate Glass
739(6)
J.A. Fortner
C.J. Mertz
A.J. Bakel
R.J. Finch
D.B. Chamberlain
The Role of Alteration Phases in Influencing the Kinetics of Glass Dissolution
745(6)
D.J. Wronkiewicz
K.A. Arbesman
Estimating Model Parameter Values for Total System Performance Assessment
751(8)
William L. Ebert
Vladislav N. Zyryanov
James C. Cunnane
Author Index 759(4)
Subject Index 763

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