Top
Note: Supplemental materials are not guaranteed with Rental or Used book purchases.
Purchase Benefits
Free Shipping On Orders Over $35!
Get Rewarded for Ordering Your Textbooks! Enroll Now
Customer Reviews Read Reviews
Write a Review
Looking to rent a book? Rent Low Temperature Plasmas Fundamentals, Technologies and Techniques [ISBN: 9783527406739] for the semester, quarter, and short term or search our site for other textbooks by Hippler, Rainer; Kersten, Holger; Schmidt, Martin; Schoenbach, Karl H.. Renting a textbook can save you up to 90% from the cost of buying.
Holger Kersten teaches as professor at the Institute of Experimental and Applied Physics, University of Kiel. He is working in the field of plasma physics and plasma technology, with emphasis on complex (dusty) plasmas, plasma surface interaction, and ion beam diagnostics.
Martin Schmidt is a leading scientist at the Institute of Low Temperature Plasma Physics in Greifswald, a center of application-oriented research which belongs to the Leibniz-Science Community.
Karl H. Schoenbach holds the Batten Endowed Chair for Bioelectrics at Old Dominion University in Norfolk, Virginia, where he serves as Director of the Frank Reidy Research Center for Bioelectrics, a center devoted to research on biological effects of cold plasma and pulsed electric fields.
| Preface | |
| Preface to 2nd Edition | |
| Basic Reactor Physics | |
| Neutron Nuclear Reactions | |
| Neutron-Induced Nuclear Fission | |
| Neutron Capture | |
| Neutron Elastic Scattering | |
| Summary of Cross-Section Data | |
| Evaluated Nuclear Data Files | |
| Elastic Scattering Kinematics | |
| Neutron Chain Fission Reactors | |
| Neutron Chain Fission Reactions | |
| Criticality | |
| Time Dependence of a Neutron Fission Chain Assembly | |
| Classification of Nuclear Reactors | |
| Neutron Diffusion Theory | |
| Derivation of One-Speed Diffusion Theory | |
| Solutions of the Neutron Diffusion Equation in Nonmultiplying Media | |
| Diffusion Kernels and Distributed Sources in a Homogeneous Medium | |
| Albedo Boundary Condition | |
| Neutron Diffusion and Migration Lengths | |
| Bare Homogeneous Reactor | |
| Reflected Reactor | |
| Homogenization of a Heterogeneous Fuel-Moderator Assembly | |
| Control Rods | |
| Numerical Solution of Diffusion Equation | |
| Nodal Approximation | |
| Transport Methods | |
| Neutron Energy Distribution | |
| Analytical Solutions in an Infinite Medium | |
| Multigroup Calculation of Neutron Energy Distribution in an Infinite Medium | |
| Resonance Absorption | |
| Multigroup Diffusion Theory | |
| Nuclear Reactor Dynamics | |
| Delayed Fission Neutrons | |
| Point Kinetics Equations | |
| Period-Reactivity Relations | |
| Approximate Solutions of the Point Neutron Kinetics Equations | |
| Delayed Neutron Kernel and Zero-Power Transfer Function | |
| Experimental Determination of Neutron Kinetics Parameters | |
| Reactivity Feedback | |
| Perturbation Theory Evaluation of Reactivity Temperature Coefficients | |
| Reactor Stability | |
| Measurement of Reactor Transfer Functions | |
| Reactor Transients with Feedback | |
| Reactor Fast Excursions | |
| Numerical Methods | |
| Fuel Burnup | |
| Changes in Fuel Composition | |
| Samarium and Xenon | |
| Fertile-to-Fissile Conversion and Breeding | |
| Simple Model of Fuel Depletion | |
| Fuel Reprocessing and Recycling | |
| Radioactive Waste | |
| Burning Surplus Weapons-Grade Uranium and Plutonium | |
| Utilization of Uranium Energy Content | |
| Transmutation of Spent Nuclear Fuel | |
| Closing the Nuclear Fuel Cycle | |
| Nuclear Power Reactors | |
| Pressurized Water Reactors | |
| Boiling Water Reactors | |
| Pressure Tube Heavy Water-Moderated Reactors | |
| Pressure Tube Graphite-Moderated Reactors | |
| Graphite-Moderated Gas-Cooled Reactors | |
| Liquid-Metal Fast Breeder Reactors | |
| Other Power Reactors | |
| Characteristics of Power Reactors | |
| Advanced Generation-III Reactors | |
| Advanced Generation-IV Reactors | |
| Advanced Sub-critical Reactors | |
| Nuclear Reactor Analysis | |
| Interaction of Reactor Physics and Reactor Thermal Hydraulics | |
| Reactor Safety | |
| Elements of Reactor Safety | |
| Reactor Safety Analysis | |
| Quantitative Risk Assessment | |
| Reactor Accidents | |
| Passive Safety | |
| Advanced Reactor Physics | |
| Neutron Transport Theory | |
| Neutron Transport Equation | |
| Integral Transport Theory | |
| Collision Probability Methods | |
| Interface Current Methods in Slab Geometry | |
| Multidimensional Interface Current Methods | |
| Spherical Harmonics (PL) Methods in One-Dimensional Geometries | |
| Multidimensional Spherical Harmonics (PL) Transport Theory | |
| Discrete Ordinates Methods in One-Dimensional Slab Geometry | |
| Discrete Ordinates Methods in One-Dimensional Spherical Geometry | |
| Multidimensional Discrete Ordinates Methods | |
| Even-Parity Transport Formulation | |
| Monte Carlo Methods | |
| Neutron Slowing Down | |
| Elastic Scattering Transfer Function | |
| P1 and B1 Slowing-Down Equations | |
| Diffusion Theory | |
| Continuous Slowing-Down | |
| Table of Contents provided by Publisher. All Rights Reserved. |
The New copy of this book will include any supplemental materials advertised. Please check the title of the book to determine if it should include any access cards, study guides, lab manuals, CDs, etc.
The Used, Rental and eBook copies of this book are not guaranteed to include any supplemental materials. Typically, only the book itself is included. This is true even if the title states it includes any access cards, study guides, lab manuals, CDs, etc.
Need Help? Copyright © 1999-2025
