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Measurement of irradiation-enhanced creep in nuclear materials : proceedings of an international conference /
Measurement of Irradiation-Enhanced Creep in Nuclear Materials covers the proceedings of an international conference organized by the commission of the European communities. The book presents 37 papers that are organized according to the session of the conference. Each session focuses on various top...
| Clasificación: | Libro Electrónico |
|---|---|
| Autores Corporativos: | , |
| Otros Autores: | , , |
| Formato: | Electrónico Congresos, conferencias eBook |
| Idioma: | Inglés |
| Publicado: |
Amsterdam :
North-Holland,
1977.
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| Colección: | EUR (Series) ;
5676. |
| Temas: | |
| Acceso en línea: | Texto completo |
Tabla de Contenidos:
- Front Cover; Measurement of Irradiation-Enhanced Creep in Nuclear Materials; Copyright Page; INTRODUCTION/PREFACE; LIST OF PARTICIPANTS; Table of Contents; Session I: Irradiation creep of ceramic nuclear fuels; CHAPTER 1. IRRADIATION INDUCED CREEP OF CERAMIC NUCLEAR FUELS; 1. Introduction; 2. Physical mechanisms for irradiation creep; 3. Measuring methods; 4. Experimental results; 5. Importance of further experiments; References; CHAPTER 2. OXIDE FUEL IN-REACTOR CREEP
- LMFBR DESIGN ASPECTS; 1. Introduction; 2. Review of fuel creep data; 3. Steady-state operation.
- 4. Transient overpower operation5. Conclusions and recommendations; Acknowledgement; References; CHAPTER 3. INTERPRETING AND PREDICTING IRRADIATION CREEP BY FUEL ELEMENT MODELLING; 1. Introduction; 2. Theoretical predictions; 3. Fuel element modelling calculations; 4. Conclusions; Appendix: Summary of data used in the modelling calculations; References; CHAPTER 4. CREEP PROPERTIES OF OXIDE AND CARBIDE FUELS UNDER IRRADIATION; 1. Introduction; 2. Experimental techniques; 3. Behaviour of UO2 under irradiation; 4. Behaviour of UC; 5. Discussion; Acknowledgements; References.
- CHAPTER 5. IN-PILE CREEP STUDY ON MIXED OXIDE (U, Pu)O21. Introduction; 2. Description of the experiments; 3. Experimental procedure; 4. Results; 5. Discussion; 6. Conclusion; References; CHAPTER 6. IN-PILE MEASUREMENT OF FISSION ENHANCED CREEP AND SWELLING OF URANIUM NITRIDE; 1. Introduction; 2. Choice of parameters; 3. Design of apparatus; 4. Analytical work; 5. Performance and measurements; 6. Post irradiation examination; 7. Discussion; Acknowledgement; References; CHAPTER 7. MEASUREMENT OF THE DIAMETRAL EVOLUTION OF A FUEL ELEMENT DURING ITS IRRADIATION. THE MEDINA SERVICE.
- 1. Introduction2. The MEDINA device; 3. MEDINA experiment X4; 4. Developments; CHAPTER 8. IRRADIATION DEVICES FOR THE STUDY OF CREEP AND SWELLING IN CERAMIC FUELS; 1. Introduction; 2. Brief description of the various irradiation devices; 3. Description of the measurement principles; 4. Experience to date; Reference; Session II: Irradiation creep of graphite; CHAPTER 9. RADIATION CREEP OF GRAPHITE. AN INTROE HJCTION; 1. The problem; 2. Experimental techniques; 3. Data and observations; 4. The mechanism of radiation creep in graphite; 5. White areas on the map; References.
- CHAPTER 10. UKAEA REACTOR GROUP STUDIES OF IRRADIATION-INDUCED CREEP IN GRAPHITE1. Introduction; 2. Experimental details; 3. Theoretical analyses; 4. Discussion; Acknowledgments; References; CHAPTER 11. REVIEW OF A TEST PROGRAMME ON IRRADIATION CREEP OF GRAPHITES AND SYSTEMISATION OF RESULTS; 1. Introduction; 2. Constant stress creep experiments; 3. Creep experiments under varying stress; References; CHAPTER 12. DESIGN, OPERATION, AND INITIAL RESULTS FROM A SERIES OF GRAPHITE CREEP IRRADIATION EXPERIMENTS; 1. Introduction; 2. Program objectives and design criteria.