Keywords:
Nuclear fuels -- Congresses.
;
Nuclear reactors -- Safety measures -- Congresses.
;
Electronic books.
Type of Medium:
Online Resource
Pages:
1 online resource (359 pages)
Edition:
1st ed.
ISBN:
9780444596833
Series Statement:
Issn Series ; v.Volume 28
URL:
https://ebookcentral.proquest.com/lib/geomar/detail.action?docID=1191020
Language:
English
Note:
Front Cover -- Nuclear Materials for Fission Reactors -- Copyright Page -- Table of Contents -- Preface -- Supporting Organizations and Sponsors -- 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 pellets -- 1. 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 II -- 1. 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.
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Chapter 9. Microstructural change and its influence on fission gas release in high burnup UO2 fuel -- 1. 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 microstructures -- 4. 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) -- 5. Microstructure Studies -- References -- Chapter 14. Fuel rod and core materials investigations related to LWR extended burnup operation -- 1. Introduction -- 2. Fuel behaviour studies -- 3. Corrosion and material testing -- 4. Summary -- References -- Section II: REACTOR SAFETY -- Chapter 15. The Phebus fission product project -- 1. Introduction -- 2. Program objectives -- 3. Facility description -- 4. Experimental sequence -- 5. Materials problems -- 6. Organisation, planning and status -- 7. Conclusions -- References.
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Chapter 16. Information on the evolution of severe LWR fuel element damage obtained in the CORA program -- 1. Introduction -- 2. CORA fuel rod bundle, test facility and test conduct -- 3. Test results and discussion -- 4. Requirements for the Modeling of fuel element degradation and meltdown -- 5. Implications on risk minimation and accident management -- Acknowledgement -- References -- Chapter 17. Fuel behaviour under severe accident conditions: Interpretation of PTE results from the CABRI test programme -- 1. Introduction -- 2. The CABRI test programme and fuel characteristics -- 3. Fuel behaviour up to pin failure -- 4. Fuel breakup and relocation -- 5. Interaction with other materials -- 6. Behaviour of fission products -- 7. Conclusions -- Abbreviations -- References -- Chapter 18. Failure behavior of plutonium-uranium mixed oxide fuel under reactivity-initiated accident condition -- 1. Introduction -- 2. Experiments -- 3. Experimental results -- 4. Discussions -- 5. Conclusions -- References -- Chapter 19. Transient fuel behavior of preirradiated PWR fuels under reactivity initiated accident conditions -- 1. Introduction -- 2. Experimental methods -- 3. Experimental results and discussion -- 4. Summary -- Acknowledgements -- References -- Chapter 20. UO2 fuel behavior under RIA type tests -- 1. Introduction -- 2. Experimental -- 3. Results -- 5. Conclusions -- Acknowledgements -- References -- Chapter 21. On the kinetics of UO2 interaction with molten Zircaloy at high temperatures -- 1. Introduction -- 2. The two-phase region formation during UO2 dissolution by molten Zr -- 3. Microscopic model for mass transfer in the two-phase region -- References -- Section III: BASIC PROPERTIES OF NUCLEAR MATERIALS -- Chapter 22. Neutron irradiation effects in boron carbides: Evolution of microstructure and thermal properties -- 1. Introduction.
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2. Experimental -- 3. Results -- 4. Discussion -- References -- Chapter 23. On the theory of high temperature transition in fluorite-type oxides -- 1. Introduction -- 2. Landau Hamiltonian -- 3. Microscopic models -- 4. Diffusion coefficient -- 5. Conclusions -- Acknowledgements -- References -- Chapter 24. Thermal conductivity of (U, Pu)O2-x mixed oxide fuel -- 1. Introduction -- 2. Choice and study of the reference fuel -- 3. Influence of deviation from stoichiometry -- 4. Influence of plutonium content -- 5. Influence of Porosity -- 6. Influence of burnup -- 7. Conclusion -- References -- Chapter 25. Thermal conductivity of SIMFUEL -- 1. Introduction -- 2. Experimental -- 3. Results and discussion -- 4. Conclusions -- References -- Chapter 26. High temperature heat capacities and electrical conductivities of UO2 doped with yttrium and simulated fission products -- 1. Introduction -- 2. Experimental -- 3. Results and discussion -- Acknowledgement -- References -- Chapter 27. Defect structure and oxygen diffusion in UO2+δ -- 1. Introduction -- 2. Theory -- 3. Experimental procedure -- 4. Results -- 5. Discussion -- 6. Conclusions -- Acknowledgements -- References -- Chapter 28. A comparison of the behaviour of fission gases in UO2±x and α-U3O8-z -- 1. Introduction -- 2. Computational techniques -- 3. The UO2 and U3O8 lattices -- 4. Gas atom trap sites -- 5. Migration mechanisms -- 6. Conclusions -- References -- Chapter 29. Effect of temperature on bubble precipitation in uranium dioxide implanted with krypton and xenon ions -- 1. Introduction -- 2. Experimental details -- 3. Results -- 4. Discussion -- Acknowledgements -- References -- Chapter 30. Investigation of nuclear mixed oxide fuel-gas interaction by a solid electrolyte based coulometric technique -- 1. Introduction -- 2. Experimental -- 3. Results and discussion -- References.
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Chapter 31. Nonideality of the solid solution in (U, Pu)O2 nuclear fuels -- 1. Introduction -- 2. Properties of the mixed oxides: experimental results -- 3. Disussion -- 4. Cation valency -- 5. Conclusion -- Acknowledgements -- References -- Chapter 32. Vaporization behavior of uranium-plutonium mixed nitride -- 1. Introduction -- 2. Experimental -- 3. Results -- 4. Discussion -- 5. Conclusions -- Acknowledgements -- References -- Chapter 33. The fate of nitrogen upon reprocessing of nitride fuels -- 1. Introduction -- 2. Experimental -- 3. Results -- 4. Discussion -- 5. Conclusion -- Acknowledgements -- References -- Chapter 34. Stability and structure of the δ phase of the U-Zr alloys -- 1. Introduction -- 2. Experimental details -- 3. Results and discussion -- 4. Conclusions -- Acknowledgements -- References -- Chapter 35. Study of the oxidation of a stainless steel under BWR conditions by advanced analytical techniques -- 1. Introduction -- 2. Experimental -- 3. Results and discussion -- 4. Conclusion -- References -- Chapter 36. Modelling of inert gas bubble behaviour during annealing of irradiated molybdenum -- 1. Introduction -- 2. Theory -- 3. Results and discussion -- 4. Conclusions -- References -- Chapter 37. Mass and gamma spectrometric measurements of fission products released from overheated, fresh irradiated, uranium dioxide -- 1. Introduction -- 2. Sample characteristics -- 3. Experimental equipment -- 4. Evaporation of irradiated fuel -- 5. Release of fission products -- 6. Discussion of the results per element -- 7. Conclusions -- References -- Chapter 38. Structural analysis of oxide scales grown on zirconium alloys in autoclaves and in a PWR -- 1. Introduction -- 2. Dissolution of zirconium-base alloys -- 3. General morphology of oxide scales -- 4. Analysis of the active layer -- 5. Conclusions -- References.
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Chapter 39. Carbon activity measurements in boron carbides using a solid state Potentiometrie cell.
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