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Radiation damage of structural materials /
Maintaining the integrity of nuclear power plants is critical in the prevention or control of severe accidents. This monograph deals with both basic groups of structural materials used in the design of light-water nuclear reactors, making the primary safety barriers of NPPs. Emphasis is placed on ma...
| Clasificación: | Libro Electrónico |
|---|---|
| Autor principal: | |
| Otros Autores: | |
| Formato: | Electrónico eBook |
| Idioma: | Inglés Checo |
| Publicado: |
Amsterdam ; New York :
Elsevier,
1994.
|
| Colección: | Materials science monographs ;
79. |
| Temas: | |
| Acceso en línea: | Texto completo Texto completo |
MARC
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| 100 | 1 | |a Koutsk�y, Jaroslav. | |
| 245 | 1 | 0 | |a Radiation damage of structural materials / |c Jaroslav Koutsk�y, Jan Ko�c�ik. |
| 264 | 1 | |a Amsterdam ; |a New York : |b Elsevier, |c 1994. | |
| 300 | |a 1 online resource (361 pages) : |b illustrations | ||
| 336 | |a text |b txt |2 rdacontent | ||
| 337 | |a computer |b c |2 rdamedia | ||
| 338 | |a online resource |b cr |2 rdacarrier | ||
| 490 | 1 | |a Materials science monographs ; |v 79 | |
| 500 | |a Translated from the Czech. | ||
| 504 | |a Includes bibliographical references and index. | ||
| 520 | |a Maintaining the integrity of nuclear power plants is critical in the prevention or control of severe accidents. This monograph deals with both basic groups of structural materials used in the design of light-water nuclear reactors, making the primary safety barriers of NPPs. Emphasis is placed on materials used in VVER-type nuclear reactors: Cr-Mo-V and Cr-Ni-Mo-V steel for RPV and Zr-Nb alloys for fuel element cladding. The book is divided into 7 main chapters, with the exception of the opening one and the chapter providing a phenomenological background for the subject of radiation damage. Chapters 3-6 are devoted to RPV steels and chapters 7-9 to zirconium alloys, analysing their radiation damage structure, changes of mechanical properties due to neutron irradiation as well as factors influencing the degree of their performance degradation. The recovery of damaged materials is also discussed. Considerable attention is paid to a comparison of VVER-type and western-type light-water materials. This monograph will be of great value to postgraduate students in nuclear engineering and materials science, and for designers and research workers in nuclear energy. | ||
| 588 | 0 | |a Print version record. | |
| 505 | 0 | |a Front Cover; Radiation Damage of Structural Materials; Copyright Page; Table of Contents; Preface; List of Symbols; Chapter 1. Introduction; References to Chapter 1; Chapter 2. Radiation Damage; 2.1 Primary Damage Processes; 2.2 Collision Cascades; 2.3 Radiation Damage Structure; References to Chapter 2; Chapter 3. Factors Affecting Radiation Damage of Steels; 3.1 Types of Steels, their Chemical Compositions and Microstructures; 3.2 The Nature of Radiation Damage; 3.3. The Irradiation Temperature; 3.4 Neutron Environment; 3.5 Stress Conditions; 3.6 Environmental Effects. | |
| 505 | 8 | |a 5.3 The Results of Research on Radiation Damage of Steel in Reactor Pressure Vessels in former Czechoslovakia5.4 Microstructure of WER Type RPV Steels; 5.5 Martensitic Ageing Steels; References to Chapter 5; Chapter 6. Experimental Determination of the Mechanism of the Recovery of 15Kh2NMFA Steel after Radiation Strengthening; 6.1 Material, Treatment and Test Samples; 6.2 Irradiation Conditions and Experimental Apparatus; 6.3 Experimental Results and their Statistical Treatment; 6.4 Discussion of the Results of the Recovery Tests. | |
| 505 | 8 | |a 6.5 Comparison of the Recovery of 15KH2NMFA Steel from Radiation Strengthening with other Types of Steel6�6 Contemporary View of the Importance of Radiation Damage for the RPV Lifetime and Expected Further Research; References to Chapter 6; Chapter 7. Radiation Damage to Zirconium and its Alloys; 7.1 Zirconium and its Alloys; 7.2 Radiation Damage Structure; References to Chapter 7; Chapter 8. Changes in the Properties of Zr Alloys as a Result of Irradiation; 8.1 Radiation Hardening; 8.2 Irradiation Growth; 8.3 Radiation Creep; References to Chapter 8. | |
| 505 | 8 | |a Chapter 9. Corrosion of Zr Alloys in Water and Steam9.1 Kinetics of Oxidation; 9.2 The Kinetics of Hydrogen Absorption; 9.3 The Corrosion Properties of Zr Alloys; 9.4 The Effect of Radiation on the Corrosion of Zr Alloys; 9.5 Oxide Properties; 9.6 The Corrosion Mechanism; 9.7 Damage to Fuel Elements as a Result of Stress Corrosion Cracking by Fission Products (SCC); References to Chapter 9; Subject Index. | |
| 650 | 0 | |a Nuclear reactors |x Materials |x Effect of radiation on. | |
| 650 | 0 | |a Steel |x Effect of radiation on. | |
| 650 | 0 | |a Steel alloys |x Effect of radiation on. | |
| 650 | 0 | |a Zirconium |x Effect of radiation on. | |
| 650 | 0 | |a Zirconium alloys |x Effect of radiation on. | |
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| 650 | 7 | |a R�eacteurs nucl�eaires |x Mat�eriaux |x Effets des rayonnements. |2 ram | |
| 650 | 7 | |a Acier |x Effets des rayonnements. |2 ram | |
| 650 | 7 | |a Aciers alli�es |x Effets des rayonnements. |2 ram | |
| 650 | 7 | |a Zirconium |x Effets des rayonnements. |2 ram | |
| 650 | 7 | |a Zirconium |x Alliages |x Effets des rayonnements. |2 ram | |
| 700 | 1 | |a Ko�c�ik, Jan, |d 1941- | |
| 776 | 0 | 8 | |i Print version: |a Koutsk�y, Jaroslav. |t Radiation damage of structural materials |z 0444987088 |w (DLC) 93000489 |w (OCoLC)27677531 |
| 830 | 0 | |a Materials science monographs ; |v 79. | |
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