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Nuclear materials for fission reactors : proceedings of Symposium E on Nuclear Materials for Fission Reactors of the 1991 E-MRS Fall Conference, Strasbourg, France, November 4-7, 1991 /
This volume brings together 47 papers from scientists involved in the fabrication of new nuclear fuels, in basic research of nuclear materials, their application and technology as well as in computer codes and modelling of fuel behaviour. The main emphasis is on progress in the development of non-ox...
| Clasificación: | Libro Electrónico |
|---|---|
| Autor Corporativo: | |
| Otros Autores: | , |
| Formato: | Electrónico Congresos, conferencias eBook |
| Idioma: | Inglés |
| Publicado: |
Amsterdam ; New York :
North-Holland,
1992.
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| Colección: | European Materials Research Society symposia proceedings ;
v. 28. |
| Temas: | |
| Acceso en línea: | Texto completo |
Tabla de Contenidos:
- Front Cover; Nuclear Materials for Fission Reactors; Copyright Page; Preface; Supporting Organizations and Sponsors; Table of Contents; Section I: FUEL FABRICATION AND PERFORMANCE; Chapter 1. Irradiation behavior of metallic fast reactor fuels; 1. Introduction; 2. Metallic fuel design; 3. Design, operating and fabrication variables testing; 4. Conclusions; Acknowledgements; References; Chapter 2. MOX fuel development: yesterday, today and tomorrow; 1. Introduction; 2. Specific features of MOX fuel; 3. Yesterday; 4. Today; 5. Tomorrow; 6. Conclusion; References
- Chapter 3. Development and characteristics of the rim region in high burnup UO2 fuel pellets1. Introduction; 2. Results; 3. Discussion; 4. Summary/conclusions; References; Chapter 4. Preparation of uranium nitride in the form of microspheres; 1. Introduction; 2. Experimental; 3. Results and Discussion; 4. Conclusions; References; Chapter 5. Mechanism and kinetics of the uranium-plutonium mononitride synthesis; 1. Introduction; 2. Synthesis of the UPuN phase; 3. Kinetics of the UPuN synthesis; 4. Conclusion; Acknowledgements; References
- Chapter 6. Irradiation of a 19 pin subassembly with mixed carbide fuel in KNK II1. Introduction; 2. Pin fabrication data; 3. Irradiation history; 4. Postirradiation examination; 5. Summary; References; Chapter 7. Fission product behaviour in Phenix fuel pins at high burnup; 1. A necessary experimental program on high burnup fuel; 2. Experimental process; 3. Discussion; 4. Main outcomes; References; Chapter 8. Fission product behaviour in fast breeder fuel pins; 1. Introduction; 2. Experimental results; 3. Discussion; 4. Conclusions; References
- Chapter 9. Microstructural change and its influence on fission gas release in high burnup UO2 fuel1. Introduction; 2. Experimental; 3. Results and discussion; Acknowledgements; References; Chapter 10 .Concerning the microstructure changes that occur at the surface of UO2 pellets on irradiation to high burnup; 1. Introduction; 2. The microstructure changes; 3. Behaviour of fission gas; 4. Depth of penetration; 5. Role of plutonium; 6. Conclusions; Acknowledgements; References; Chapter 11. Microstructural analysis of LWR spent fuels at high burnup; 1. Introduction; 2. Experimental
- 3. Temperature-dependent fuel microstructures4. Rim microstructure; 5. Discussion; 6. Conclusions; Acknowledgement; References; Chapter 12. Transmission electron microscopy study of fission product behaviour in high burnup UO2; 1. Introduction; 2. Sample preparation and examination; 4. Conclusions; Acknowledgements; References; Chapter 13. Fuel performance under normal PWR conditions: A review of relevant experimental results and models; 1. Introduction; 2. Experimental equipment; 3. Experimental results for overall UO2 fuel rod behaviour; 4. In-pile behaviour of special fuels (BOL)