Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors

 
 
Springer (Verlag)
  • erschienen am 17. Juli 2017
  • |
  • MMCDLXXII, 2354 Seiten
 
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978-3-319-48760-1 (ISBN)
 
This 15th Edition of the International Conference on Materials Degradation in Light Water Reactors focuses on subject areas critical to the safe and efficient running of nuclear reactor systems through the exchange and discussion of reseach results as well as field operating and management experience.
1st ed. 2016
  • Englisch
  • Cham
  • |
  • Schweiz
Springer International Publishing
Bibliographie
  • 509,87 MB
978-3-319-48760-1 (9783319487601)
10.1007/978-3-319-48760-1
weitere Ausgaben werden ermittelt
The Minerals, Metals & Materials Society (TMS) is a member-driven international professional society dedicated to fostering the exchange of learning and ideas across the entire range of materials science and engineering, from minerals processing and primary metals production, to basic research and the advanced applications of materials. Included among its nearly 13,000 professional and student members are metallurgical and materials engineers, scientists, researchers, educators, and administrators from more than 70 countries on six continents. For more information on TMS, visit www.tms.org.
  • Cover
  • Title Page
  • Copyright Page
  • Table of Contents
  • Preface
  • Conference Organizing Committee/Program Committee
  • Session Chairs and Technical Reviewers
  • Student Volunteers
  • Financial Sponsors
  • Opening Session
  • Overview of NRC Proactive Management of Materials Degradation (PMMD) Program
  • Questions & Answers
  • Conditions for Long Term Operation of Nuclear Power Plants in Sweden
  • Alloy 690 and Its Weld Metals I
  • Current NRC Perspectives Concerning Primary Water Stress Corrosion Cracking
  • Questions & Answers
  • Evaluation of the Susceptibility to SCC Initiation of Alloy 690 in Simulated PWR Primary Water
  • Questions & Answers
  • Role of Cavity Formation on Crack Growth of Cold-Worked Carbon Steel, TT 690 and MA 600 in High Temperature Water
  • Crack Growth Testing on Cold Worked Alloy 690 in Primary Water Environment
  • Questions & Answers
  • One-Dimensional Cold Rolling Effects on Stress Corrosion Crack Growth in Alloy 690 Tubing and Plate Materials
  • Questions & Answers
  • Alloy 690 and Its Weld Metals II
  • Cyclic and SCC Behavior of Alloy 690 HAZ in a PWR Environment
  • Questions & Answers
  • Stress Corrosion Crack Growth Rate Testing of Novel Composite Arrest Specimens
  • Questions & Answers
  • Environmentally Assisted Crack Growth in Cold Worked Alloy 690TT in Primary Water at Low and High Temperatures
  • Questions & Answers
  • SCC of Alloy 690 and Its Weld Metals
  • Questions & Answers
  • SCC Behavior of Alloy 152 Weld in PWR Environment
  • Alloy 690 and Its Weld Metals III
  • Effect of Hot Cracks on EAC Crack Initiation and Growth in Nickel-Base Alloy Weld Metals
  • Questions & Answers
  • Stress Corrosion Crack Growth of Alloy 52M in Simulated PWR Primary Water
  • Cyclic and SCC Behavior of Alloy 52M/182 Weld Overlay in a PWR Environment
  • SCC of High Cr Alloys in BWR Environments
  • Questions & Answers
  • High-Resolution Characterizations of Grain Boundary Damage and Stress Corrosion Crack Tips in Cold-Rolled Alloy 690
  • Alloy 690 and Its Weld Metals IV
  • Research and Evaluation of Low Temperature Crack Propagation of Ni Base Alloys in Actual Plants
  • Questions & Answers
  • Penetrative Internal Oxidation from Alloy 690 Surfaces and Stress Corrosion Crack Walls during Exposure to PWR Primary Water
  • Predicting Chromium Depletion of Nickel-Base Alloys
  • Questions & Answers
  • BWR Initiation and Oxide Film Characterization I
  • In-situ and Ex-situ Oxide Characterization by Synchrotron X-ray (SPring-8) in Non-Sensitized 316 Stainless Steel and High Temperature Water Combination
  • Questions & Answers
  • High Resolution Electron Microscopy Study on Oxide Films Formed on Nickel-Base Alloys X-750, 182 and 82 in Simulated High Flow Velocity BWR Water Conditions
  • Questions & Answers
  • Destructive Examinations on Divider Plates from Decommissioned Steam Generators Affected by Superficial Stress Corrosion Cracks
  • Questions & Answers
  • Non-linear Dynamics of the Morphology at the Oxide / Metal Interface of Austenitic Steels in Simulated Light Water Reactor Environments and Its Implications for SCC Initiation
  • Questions & Answers
  • BWR Initiation and Oxide Film Characterization II
  • The Effect of Cold Work on Microstructure and SCC Susceptibility in Simulated BWR Environment for Non-Sensitized Austenitic Stainless Steels
  • Behavior of Stress Corrosion Cracking for Type 316L Stainless Steel with Controlled Distribution of Surface Work Hardened Layer in Simulated Boiling Water Reactors Environment
  • Questions & Answers
  • Influence of Bulk and Surface Cold Work on Crack Initiation and Crack Growth of Austenitic Stainless Steels under Simulated BWR Environment
  • Questions & Answers
  • BWR Stainless Steels CGR I
  • Effect of Nitrogen Addition in 304 L Stainless Steel on the IGSCC Crack Growth Rate in Simulated BWR Environment
  • Questions & Answers
  • Characterization of Type 304L Stainless Steel: Comparison of ASTM A262 Practice A and Analytical Electron Microscopy Techniques
  • Questions & Answers
  • BWR Stainless Steels CGR II
  • The Effect of Grain Size on IGSCC in SS 316L in Simulated BWR Environment
  • Questions & Answers
  • An Investigation into Stress Corrosion Cracking of Dissimilar Metal Welds with 304L Stainless Steel and Alloy 82 in High Temperature Pure Water
  • Questions & Answers
  • Deformation Mode and Microstructure on Stress Corrosion Cracking Path and Kinetics in High Temperature Water Environments
  • Questions & Answers
  • Corrosion Fatigue - BWR, PWR
  • Effect of Static Load Hold Periods on the Corrosion Fatigue Behavior of Austenitic Stainless Steels in Simulated BWR Environments
  • Effects of Material Composition on Corrosion Fatigue Crack Growth of Austenitic Stainless Steels in High Temperature Water
  • Questions & Answers
  • Fatigue Limit and Hysteresis Behavior of Type 304l SS in Air and PWR Water, at 150°C and 300°C
  • NRC Research Activities on Environmentally-Assisted Fatigue
  • Questions & Answers
  • Fuel and Fuel Related Materials I
  • PWR Fuel Deposit Analysis at a B&W Plant with a 24-Month Fuel Cycle
  • Questions & Answers
  • Effect of DH Concentration on Crud Deposition on Heated Zircaloy-4 in Simulated PWR Primary Water
  • Questions & Answers
  • Use of AREVA BWR CRUD Model To Study High Zinc Operation at a US Plant
  • Electrochemical Study of Pre- and Post-Transition Corrosion of Zr Alloys in PWR Coolant
  • AREVA Fuel Condition Index for a Pressurized Water Reactor
  • Fuel and Fuel Related Materials II
  • Structure and Thermodynamical Properties of Zirconium Hydrides from First-Principle
  • Questions & Answers
  • Hydride Behavior in Zircaloy-4 during Thermomechanical Cycling
  • Fuel and Fuel Related Materials III PWR-BWR
  • Development of a Method for Studying the Influence of Stress State on the Iodine-Induced Stress Corrosion Cracking of Zirconium Alloys
  • Wear of Zircaloy-4 Grid Straps Due to Fretting and Periodic Impact with RV Internals Baffle Plates
  • Questions & Answers
  • Alloy 718 and X-750
  • Microstructure and SCC of Alloy X-750
  • Questions & Answers
  • Stress Corrosion Cracking and Crack Tip Characterization of Alloy X-750 in Boiling Water Reactor Environments
  • Questions & Answers
  • SCC Properties of Modified Alloy 718 in BWR Plant
  • Questions & Answers
  • Influence of Chloride Ions as Contaminants on the Corrosion Behavior of Alloy 718 in Pool Water of Nuclear Power Plants
  • BWR Low Alloy Steel
  • Stress Corrosion Cracking Behavior near the Fusion Boundary of Dissimilar Weld Joint with Alloy 182 - A533B Low Alloy Steel
  • Questions & Answers
  • Effect of Chloride on Environmentally Assisted Cracking of Low Alloy Steels in Oxygenated Hightemperature Water - General Corrosion
  • Questions & Answers
  • BWR Stainless Steels CGR III
  • The Effect of Temperature on the Crack Growth Rate in Simulated BWR Environment
  • Questions & Answers
  • Effects of Temperature and Corrosion Potential on SCC
  • Questions & Answers
  • Effect of Thermal Aging on SCC, Material Properties and Fracture Toughness of Stainless Steel Weld Metals
  • Questions & Answers
  • Flow Assisted Corrosion
  • Flow Accelerated Corrosion of Carbon Steel in the Feedwater System of Pwr Plants - Behaviour of Welds and Weld Assemblies
  • Questions & Answers
  • Modelling Material Effects in Flow-Accelerated Corrosion
  • PWR Oxide Films and Characterization
  • 3D Atom-Probe Characterization of Stress and Cold-Work in Stress Corrosion Cracking of 304 Stainless Steel
  • Questions & Answers
  • Effect of Dissolved Hydrogen, Surface Conditions and Composition on the Electronic Properties of the Oxide Films Formed on Nickel-Base Alloys in PWR Primary Water
  • Questions & Answers
  • Influence of Primary Water Chemistry on Oxides Formed on Alloy 600 and Alloy690
  • Characterizing Environmental Degradation in PWRs by 3D FIB Sequential Sectioning
  • Questions & Answers
  • PWR Secondary Side/Balance of Plant I
  • On the Microstructure of Alloy 600 SCC Cracks Observed by TEM on PWR SG Pulled Tubes and on Laboratory Specimens
  • Balance of Plant Corrosion Issues in Aging Nuclear Power Plants
  • Questions & Answers
  • Containment Liner Corrosion
  • Questions & Answers
  • PWR Secondary Side/Balance of Plant II
  • Electrochemical Studies of Steam Generator Tube Degradation in the Presence of Thiosulphate
  • Questions & Answers
  • X-Ray Photoelectron Study of the Oxides Formed on Nickel Metal and Nickel-Chromium 20% Alloy Surfaces under Reducing and Oxidizing Potentials in Basic, Neutral and Acidic Solutions
  • Questions & Answers
  • SCC of Alloy 82, 182 Welds I
  • Interaction of Microstructure, Composition, and Cold Work on the Stress Corrosion Cracking of Alloy 82 Weld Metal
  • Questions & Answers
  • Stress Corrosion Cracking Behavior of Dissimilar Metal Weldments in High Temperature Water Environment
  • Questions & Answers
  • SCC Crack Growth Rate of Alloy 82 in PWR Primary Water Conditions - Effect of a Thermal Treatment
  • SCC of Alloy 82, 182 Welds II
  • Initiation of PWSCC of Weld Alloys 182
  • Questions & Answers
  • NRC/EPRI Welding Residual Stress Validation Program (Phase III)
  • Questions & Answers
  • IASCC Stainless Steels CGR I
  • Crack Growth Behavior of Irradiated Type 316 SS in Low Dissolved Oxygen Environment
  • Questions & Answers
  • Stress Corrosion Crack Initiation Susceptibility of Irradiated Austenitic Stainless Steels
  • Questions & Answers
  • Stress Corrosion Cracking Behavior of Type 304 Stainless Steel Irradiated under Different Neutron Dose Rates at JMTR
  • Questions & Answers
  • In-Pile Tests for IASCC Growth Behavior of Irradiated 316L Stainless Steel under Simulated BWR Condition in JMTR
  • Crack Growth Rates of Irradiated Commercial Stainless Steels in BWR and PWR Environments
  • IASCC Stainless Steels CGR II
  • The Key Factors Affecting Crack Growth Behavior of Neutron-Irradiated Austenitic Alloys
  • Questions & Answers
  • Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steel WWER Reactor Core Internals
  • Questions & Answers
  • Slow Strain Rate Tensile Tests of Irradiated Austenitic Stainless Steels in Simulated PWR Environment
  • Questions & Answers
  • Irradiation Assisted Stress Corrosion Cracking of Stainless Steels in a PWR Environment (A Combined Approach)
  • A Preliminary Hybrid Model of Irradiation-Assisted Stress Corrosion Cracking of 300 Series Stainless Steels in PWR Primary Environments
  • Questions & Answers
  • Irradiation Effects - General I
  • Oxidation of a Proton-irradiated 316 Stainless Steel in Simulated BWR NWC Environment
  • Irradiation Creep and Irradiation Stress Relaxation of 316 and 304l Stainless Steels in Thermal and Fast Neutron Spectrum Reactors
  • Questions & Answers
  • Recent Insights on the Parametric Dependence of Irradiation Creep of Austenitic Stainless Steels
  • Questions & Answers
  • Cluster Dynamics Prediction of the Microstructure Evolution of 300-series Austenitic Stainless Steel under Irradiation: Influence of Helium
  • Irradiation Effects on Deformation
  • Role of Slip Behavior in the Irradiation Assisted Stress Corrosion Cracking in Austenitic Steels
  • Questions & Answers
  • Effect of Environment and Prestrain on IASCC of Austenitic Stainless Steels
  • Questions & Answers
  • Influence of Localized Plasticity on IASCC Sensitivity of Austenitic Stainless Steels under PWR Primary Water
  • Deformation Microstructures of 30 dpa AISI 304 Stainless Steel after Monotonic Tensile and Constant Load Autoclave Testing
  • Questions & Answers
  • PWR Alloy 600 Oxidation and Mechanisms I
  • Degradation of Grain Boundary Strength by Oxidation in Alloy 600
  • Questions & Answers
  • Evaluation of the Oxygen Diffusion Coefficient in Nickel-Base Alloys
  • Stress Corrosion Cracking of Alloy 600 in PWR Primary Water: Influence of Chromium, Oxygen and Hydrogen Diffusion
  • Questions & Answers
  • Grain Boundary Oxidation and Embrittlement Prior to Crack Initiation in Alloy 600 in PWR Primary Water
  • PWR Alloy 600 Oxidation and Mechanisms II
  • Electron Microscopy Characterizations and Atom Probe Tomography of Intergranular Attack in Alloy 600 Exposed to PWR Primary Water
  • Questions & Answers
  • Grain Boundary Oxidation and Stress Corrosion Cracking in Nickel-base Alloys Strained in Supercritical Water
  • Questions & Answers
  • Quantitative Micro-nano (QMN) Approach to SCC Mechanism and Prediction-Starting a Third Meeting
  • Questions & Answers
  • PWR Alloy 600 SCC I
  • Strain Path Effect on IGSCC Initiation and Oxidation of Alloy 182 Exposed to PWR Primary Water
  • Questions & Answers
  • Experimental Study of Short Crack Coalescence in Nickel-Base Alloys In PWR Primary Water
  • Questions & Answers
  • Mechanistic Study on PWSCC of Ni-Based Alloys Using Hump-SSRT Tests under Dry Hydrogen Gas Environment, Simulated Primary Water and Rapid Straining Electrode Test in Simulated Primary Water
  • Questions & Answers
  • Crystallographical Characterization of Initiation of Intergranular Stress Corrosion Cracking of Alloy 600 in PWR Environment
  • Questions & Answers
  • Environmental Effects on PWSCC Initiation and Propagation in Alloy 600
  • Questions & Answers
  • PWR Alloy 600 SCC II
  • Probabilistic Environmentally-Assisted Cracking Modeling for Primary Water Stress Corrosion Cracking of Alloy 600
  • Questions & Answers
  • The Role of Lattice Curvature on the SCC Susceptibility of Alloy 600
  • Questions & Answers
  • PWSCC Susceptibility in Heat-Affected Zones of Alloy 600
  • Questions & Answers
  • Quantitative Residual Strain Analyses on Strain Hardened Nickel Based Alloy
  • The Study of Stress Corrosion Cracking on Alloy 600 C-Ring Samples by Polychromatic X-Ray Microdiffraction
  • Questions & Answers
  • PWR Degradation Management
  • Proposed Coordinated U.S. PWR Reactor Vessel Surveillance Program: An Updated Summary Including Program Optimization
  • Developing PWR Aging-Management Strategies for Reactor Vessel Internals
  • Development of the Extremely Low Probability of Rupture (xLPR) Code
  • Questions & Answers
  • Databases of Operationally Induced Damage
  • Questions & Answers
  • PWR Water Chemistry and Mitigation
  • Introduction to a New Real-Time Water Chemistry Measurement System
  • Questions & Answers
  • Comparison of DBU, NH3, DMA, ETA, and Morpholine Interactions with Ferrous Chloride Solution and Carbon Steel Surfaces
  • Questions & Answers
  • Role of Dissolved Hydrogen in Water in Corrosion of Alloy 600 in High Temperature Water
  • Questions & Answers
  • Quantifying the Benefit of Chemical Mitigation of PWSCC via Zinc Addition or Hydrogen Optimization
  • Questions & Answers
  • Super Critical Water
  • Computational Thermodynamics for Interpreting Oxidation of Structural Materials in Supercritical Water
  • Questions & Answers
  • Stress Corrosion Cracking of Austenitic Alloys in Supercritical Water
  • Questions & Answers
  • Comparison of the Oxidation Behavior of the 14Cr ODS Alloy in Steam and Supercritical Water
  • Questions & Answers
  • Grain Boundary Engineering and Air Oxidation Behavior of Alloy 690
  • Questions & Answers
  • BWR Water Chemistry and Mitigation I
  • Developments in SCC Mitigation by Electrocatalysis
  • Questions & Answers
  • Use of Noble Metal Nanoparticle for SCC Mitigation in BWRs
  • Questions & Answers
  • The Influence of Minor Additions of Platinum Group Metals on Stress Corrosion Cracking in Austenitic Stainless Steels
  • Questions & Answers
  • The Effect of On-Line Noble Metal Addition on the Shut Down Dose Rates of Boiling Water Reactors
  • Questions & Answers
  • Effects of Hydrogen on SCC Growth Rate of Ni Alloys in BWR Water
  • Technical Basis for Water Chemistry Control of IGSCC in Boiling Water Reactors
  • Questions & Answers
  • BWR Water Chemistry and Mitigation II
  • Water Chemistry in the Primary Coolant Circuit of a Boiling Water Reactor during Startup Operations
  • Simulation of Water Radiolysis by Sonochemistry: Effects on the Electrochemical Behavior of a Stainless Steel
  • Questions & Answers
  • Protective Insulated Coating for SCC Mitigation in BWRs
  • Questions & Answers
  • Influence of Treating Temperature on the Deposition of TiO2 on Type 304 Stainless Steels for Corrosion Mitigation in High Temperature Pure Water
  • Questions & Answers
  • Irradiation Effects - General II
  • Irradiation Microstructure of Austenitic Steels and Cast Steels Irradiated in the BOR-60 Reactor at 320°C
  • Questions & Answers
  • PWR Field Experience I
  • Laboratory Stress Corrosion Cracking Propagation in a Superficial Cold-Worked Layer in SG Divider Plates in Alloy 600
  • Destructive Examinations on Divider Plates from Decommissionned Steam Generators Affectined by Superficial Stress Corrosion Cracks
  • Questions & Answers
  • Investigations on Core Basket Bolts from a VVER 440 Power Plant
  • Questions & Answers
  • Laboratory Analysis of a Reactor Coolant Pump Seal
  • PWSCC of Thermocoax Pressurizer Heaters in Austenitic Stainless Steel and Remedial Actions to Preventing SCC
  • PWR Field Experience II
  • Residual Stress Measurement and the Effect of Heat Treatment in Cladded Control Rod Drive Specimens
  • Questions & Answers
  • Detailed Root Cause Analysis of SG Tube ODSCC Indications within the Tube Sheets of NPP Biblis Unit A
  • Questions & Answers
  • Laboratory Investigation of a Leaking Type 316 Socket Weld in a Boron Injection Tank Sampling Line
  • Pressure Tests on SG Pulled Tubes at TSP Level
  • Implications of Steam Generator Fouling on the Degradation of Thermal and Material Performance
  • Questions & Answers
  • Key Issues Related to Corrosion Protection of Brackish Water and Sea Water Bearing Components in Cooling Water Systems
  • PWR Initiation and CGR Stainless Steels I
  • Understanding the Limits of Lattice Orientation Data Analysis in Environmental Degradation Studies
  • Questions & Answers
  • A Microstructural Investigation on the Effect of Cold Work on Environmentally Assisted Cracking of Austenitic Stainless Steels
  • Questions & Answers
  • Plastic Strain and Residual Stress Distributions in an AISI 304 Stainless Steel BWR Pipe Weld
  • Assessment of Lean Grade Duplex Stainless Steels for Nuclear Power Applications
  • PWR Initiation and CGR Stainless Steels II
  • Effects of Thermo-Mechanical Treatments on Deformation Behavior and IGSCC Susceptibility of Stainless Steels in PWR Primary Water Chemistry
  • Questions & Answers
  • Previously Unpublished Manuscripts from the 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, 23-29th August 2009, Virginia Beach, VA, USA
  • SCC Initiation Testing of Alloy 600 in High Temperature Water
  • The Effects of Deaerated Water on the Toughness of Nickel-based Alloys
  • Physical Metallurgy, Weldability, and In-service Performance of Nickel-chromium Filler Metals Used in Nuclear Power Systems
  • Author Index
  • Subject Index
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