Nuclear Materials
Nova Science Publishers Inc (Verlag)
978-1-61324-010-6 (ISBN)
In this book, the authors gather topical research in the study of nuclear materials. Topics discussed include experimental studies in nuclear fuel alloys for research reactors; the removal of arsenic from ground and surface waters using lanthanides; microstructural characterisation of zirconium based alloys and current trends in the mathematical modelling and simulation of fission product transport from fuel to primary coolant of PWRs.
Preface; Co-Precipitation Model Coupled with Predictive Model for the Removal of Arsenic from Ground & Surface Waters using Lanthanides; Experimental Studies & First Principles Calculations in Nuclear Fuel Alloys for Research Reactors; Radiation Damage & Recovery of Crystals: Frenkel vs. Schottky Defect Production; Fuel Restructuring & Actinide Radial Redistributions in Americium-Containing Uranium-Plutonium Mixed Oxide Fuels Irradiated in a Fast Reactor; Microstructural Characterization of Structural Materials of Pressurized Heavy Water Reactor; Current Trends in Mathematical Modeling & Simulation of Fission Product Transport from Fuel to Primary Coolant of PWRs; Radiation Shielding Properties of Bismuth-Based on Difference Glass Matrices: A Comparative Study on Silicate & Borate Glass; Plasma-Driven Deuterium Retention in Tungsten; Recent Advances in Molecular Dynamics Modelling of Radiation Effects in Zr; Index.
| Verlagsort | New York |
|---|---|
| Sprache | englisch |
| Maße | 260 x 180 mm |
| Gewicht | 612 g |
| Themenwelt | Naturwissenschaften ► Physik / Astronomie |
| Technik ► Elektrotechnik / Energietechnik | |
| ISBN-10 | 1-61324-010-4 / 1613240104 |
| ISBN-13 | 978-1-61324-010-6 / 9781613240106 |
| Zustand | Neuware |
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