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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
Title:
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
Author:
Symposium E on Nuclear Materials for Fission Reactors (1991 : Strasbourg, France)
ISBN:
9780444596833
Publication Information:
Amsterdam ; New York : North-Holland, 1992.
Physical Description:
1 online resource (x, 348 pages) : illustrations.
Series:
European Materials Research Society symposia proceedings ; v. 28
European Materials Research Society symposia proceedings ; v. 28.
Contents:
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)
Abstract:
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-oxide fuels besides reporting advances in the more conventional oxide fuels. The two currently performed large reactor safety programmes CORA and PHEBUS-FP are described in invited lectures. The contributions review basic property measurements, as well as the present state of fuel performance modelling. The performance of today's nuclear fuel, hence UO2 , at high burnup is also reviewed with particular emphasis on the recently observed phenomenon of grain subdivision in the cold part of the oxide fuel at high burnup, the so-called "rim" effect. Similar phenomena can be simulated by ion implantation in order to better elucidate the underlying mechanism and reviews on high resolution electron microscopy provide further information. The papers will provide a useful treatise of views, ideas and new results for all those scientists and engineers involved in the specific questions of current nuclear waste management.
Electronic Access:
ScienceDirect http://www.sciencedirect.com/science/book/9780444895714Available:*
Shelf Number | Item Barcode | Shelf Location | Status |
|---|---|---|---|
| TK9202 .S832 1991 | 1178196-1001 | Elsevier E-Book Collections | Searching... |
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