Download Recycling of plutonium and uranium in water reactor fuel : proceedings of a Technical Committee meeting held in Newby Bridge, Windermere, United Kingdom, 3-7 July 1995 PDF

TitleRecycling of plutonium and uranium in water reactor fuel : proceedings of a Technical Committee meeting held in Newby Bridge, Windermere, United Kingdom, 3-7 July 1995
File Size25.0 MB
Total Pages370
Table of Contents
                            COVER
FOREWORD
CONTENTS
SUMMARY
	1. INTRODUCTION
	2. MOX FABRICATION - Panel 1
	3. MOX FUEL PERFORMANCE - Panel 2
	4. UTILIZATION OF WEAPONS-GRADE PLUTONIUM IN MOX FUEL - Panel 3
SESSION 1 MOX RECYCLED URANIUM FUEL UTILIZATION
	MOX IN FRANCE: STATUS AND PROSPECTS
		Abstract
		1. INTRODUCTION
		2. SPENT FUEL REPROCESSING
		3. MANUFACTURING FACILITIES
		4. IN- REACTOR RECYCLING
		5. PROSPECTS
		CONCLUSION
	BASIC EVALUATION ON NUCLEAR CHARACTERISTICS OF BWR HIGH BURNUP MOX FUEL AND CORE
		Abstract
		1. INTRODUCTION
		2. STATUS OF U02 AND MOX FUEL DEVELOPMENTS
		3. HIGH BURNUP MOX FUEL AND CORE
		4. CONCLUSION
		REFERENCES
	PLUTONIUM RECYCLING: THE POINT OF VIEW OF ELECTRICITE DE FRANCE
		Abstract
		1. ANALYSIS OF EXPERIENCE FEEDBACK FROM MANAGEMENT OF MOX FUEL
		2. THE PRESENT STRATEGY
	MIXED OXIDE FUEL DEVELOPMENT FOR THE INDIAN NUCLEAR POWER PROGRAMME
		Abstract
		1. INTRODUCTION
		2. MOX FUEL FOR PHWRS
		3. MOX FUEL FOR BWRS
		4. DEVELOPMENT AND MANUFACTURE OF MOX FUEL
		5. QUALITY CONTROL DURING MOX FUEL MANUFACTURE
		6. CONCLUSIONS
		REFERENCES
	BNFL SUPPLY OF MOX FUEL ASSEMBLIES TO THE BEZNAU 1 PWR OF NOK
		Abstract
		1. INTRODUCTION
		2. NOK'S RECYCLE PHILOSOPHY AND THE APPROACH TO USING A NEW SUPPLIER
		3. THE MOX FUEL ASSEMBLY CHARACTERISTICS AND APPROACH TO LICENSING THE DESIGN
		4. FABRICATION PROCESS USED BY BNFL
		5. QUALITY CHARACTERISTICS OF BNFL MOX FUEL PELLETS
		6. LESSONS LEARNT DURING THE EARLY STAGES OF OPERATING MDF
		7. POST-IRRADIATION EXAMINATION PROGRAMME
		8. SUMMARY AND CONCLUSIONS
		ACKNOWLEDGEMENT
SESSION 2 MOX FABRICATION AND REPROCESSING
	TECHNICAL DESIGN CONSIDERATIONS IN THE PROVISION OF A COMMERCIAL MOX PLANT
		Abstract
		1. INTRODUCTION
		2. PLANT OUTLINE
		3. DESIGN ANALYSIS
		4. EQUIPMENT RELIABILITY AND THROUGHPUT
		5. SAFETY CONSIDERATIONS
		6. SUMMARY
	MOX FUEL FABRICATION EXPERIENCE AT BELGONUCLEAIRE
		Abstract
		1. INTRODUCTION
		2. MOX FABRICATION : 1986-1994
		3. BELGONUCLEAIRE MIMAS MOX FUEL IRRADIATION EXPERIENCE
		4. THE MOX FABRICATION: BEYOND 2000
		5. CONCLUSION
		REFERENCES
	PLUTONIUM RECYCLING AND THE MELOX FABRICATION PLANT
	USE OF VIBRO COMPACTED MOX FUEL IN THERMAL REACTORS
		Abstract
		1. INTRODUCTION
		2. METHODS OF COST REDUCTION
		3. METHODS OF IMPROVING DIVERSION RESISTANCE
		4. PAST EXPERIENCE - THE USE OF VIBRO FUEL IN FAST BREEDER REACTORS
		5. ASPECTS OF VIBRO MOX FUEL TO BE CONSIDERED IN THEIR APPLICATION TO THERMAL REACTORS
		6. CONCLUSIONS
		ACKNOWLEDGEMENTS
		REFERENCES
	CHANGES IN UO2 POWDER PROPERTIES DURING PROCESSING VIA BNFL'S BINDERLESS ROUTE
		Abstract
		1. INTRODUCTION
		2. EXPERIMENTAL
		3. RESULTS AND DISCUSSION
		4. PLANT SCALE BEHAVIOUR
		5. CONCLUSIONS
	MECHANISMS OF DRY BALL MILLING IN MOX FABRICATION
		Abstract
		1. INTRODUCTION
		2. MECHANISMS OF DRY BALL MILLING
		3. CHARACTERIZATION OF MILLED AND BLENDED POWDERS
		4. CONCLUSION
		REFERENCES
	CATION DIFFUSION AND CRYSTAL GROWTH AT THE UO2-PuO2 INTERFACE
		Abstract
		INTRODUCTION
		EXPERIMENTAL METHOD
		RESULTS AND DISCUSSION
		CONCLUSION
		REFERENCES
	ADVANCED ANALYSIS TECHNOLOGY FOR MOX FUEL
		Abstract
		1. INTRODUCTION
		2. DETERMINATION OF OXYGEN TO METAL ATOMIC RATIO IN MOX BY NONDISPERSIVE INFRARED SPECTROPHOTOMETRY AFTER INERT GAS FUSION
		3. DETERMINATION OF OCCLUDED GAS COMPONENT ANALYSIS IN MOX USING GAS SAMPLING UNIT AND GAS CHROMATOGRAPHY
		4. DETERMINATION OF NITROGEN IN MOX BY GAS CHROMATOGRAPHY AFTER INERT GAS FUSION
		5. FUTURE PLANS
		REFERENCES
SESSION 3 MOX FUEL DESIGN
	MOX FUEL DESIGN AND DEVELOPMENT CONSIDERATION
		Abstract
		1. INTRODUCTION
		2. OUTLINE OF PWR MOX FUEL ASSEMBLY
		3. FUEL MECHANICAL DESIGN OF MOX FUEL
		4. NUCLEAR DESIGN OF MOX FUEL
		5. FUTURE DESIGN CONSIDERATION OF PWR MOX FUEL
		6. CONCLUSION
		REFERENCES
	AN ADVANCED BWR MOX FUEL DESIGN CONCEPT FOR JAPANESE LWR PLUTONIUM RECYCLING
		Abstract
		1. INTRODUCTION
		2. ADVANCED BWR MOX FUEL DESIGN
		3. FUEL CYCLE COSTS OF MOX FUEL
		4. COMMON USE OF PU ENRICHMENT FOR PWR AND BWR MOX FUELS
		5. CONCLUSION
		REFERENCES
	TECHNOLOGY DEVELOPMENTS FOR JAPANESE BWR MOX FUEL UTILIZATION
		Abstract
		1. INTRODUCTION
		2. DESIGN STUDY OF BWR-MOX CORE AND FUEL
		3. MOX FUEL IRRADIATION STUDIES
		4. DEVELOPMENT OF MOX FUEL FABRICATION TECHNOLOGY
		5. CONCLUSION
		REFERENCES
	A REVIEW OF MULTIPLE RECYCLE OF PLUTONIUM IN LWRS
		Abstract
		1. WHY MULTIPLE RECYCLE?
		2. PHYSICS OF MULTIPLE RECYCLE
		3. MULTIPLE-RECYCLE SCENARIOS
		4. MATERIALS BALANCE
		5. CONCLUSIONS
		REFERENCES
	EVALUATION OF THE MAXIMUM CONTENT OF A MOX-FUELED PRESSURIZED WATER REACTOR VERSUS ISOTOPIC COMPOSITION WITH RESPECT TO THE VOID COEFFICIENT
		Abstract
		1. INTRODUCTION
		2. DEFINITIONS AND OBJECTIVES
		3. MODELLING. CALCULATION PLAN
		4. FORMULATION OF THE LIMIT CONTENT T,
		5. ANALYSIS OF THE GLOBAL VOID AGE IN A 100 % MOX PWR
		6. CONCLUSION
		ACKNOWLEDGEMENTS
		REFERENCES
	VENUS: A TOOL FOR THE RESEARCH OF THE NEUTRONIC BEHAVIOUR OF PU AND U FUEL
		Abstract
		1. INTRODUCTION
		2. DESCRIPTION OF THE VENUS FACILITY
		3. MEASURED PARAMETERS AND UNCERTAINTIES
		4. RECENT PROGRAMMES PERFORMED AT THE VENUS REACTOR
		5. FUTURE PROGRAMMES TO BE PERFORMED AT THE VENUS REACTOR
		6. CONCLUSIONS
		REFERENCES
	MEASUREMENT AND ANALYSIS OF MOX PHYSICAL PROPERTIES
		Abstract
		1. INTRODUCTION
		2. SAMPLE FABRICATION
		3. METHODOLOGY
		4. THERMAL DIFFUSIVITY
		5. MELTING POINT
		6. THERMAL EXPANSION
		7. CONCLUSIONS
		ACKNOWLEDGEMENTS
		REFERENCES
	NEUTRONIC FEASIBILITY OF PWR CORE WITH MIXED OXIDE FUELS IN THE REPUBLIC OF KOREA
		Abstract
		1. INTRODUCTION
		2. OPTIONS FOR RECYCLING SPENT FUELS IN KOREA
		3. MOX FUEL ASSEMBLY DESIGN
		4. FUEL MANAGEMENT STUDIES FOR MOX PART-LOADED CORES
		5. CONCLUSIONS
		REFERENCES
SESSION 4 PLUTONIUM DISPOSAL
	COULD WEAPON-GRADE PLUTONIUM BE AN ASSET FOR MANAGING PU INVENTORIES?
		Abstract
		1. INTRODUCTION
		2. COMPARISON OF Pu UTILIZATION ALTERNATIVES
		3. Pu INVENTORY
		4. MOX FABRICATION
		5. Pu CHARACTERISTICS
		6. EXTERNALITIES
		7. INCENTIVE TO INTRODUCE WPu IN A GLOBAL Pu MANAGEMENT PLAN
		8. CONCLUSION
		References
		APPENDIX
	A ONCE THROUGH SCHEME FOR WEAPONS GRADE PLUTONIUM DISPOSITION IN LWRS: PROLIFERATION AND CRITICALITY ASPECTS
		Abstract
		1. INTRODUCTION
		2. CALCULATIONAL DETAILS
		3. PROLIFERATION ASPECTS OF INERT MATRIX-BASED MIXED U-PU FISSILE MATERIAL
		4. CRIT1CALITY ASPECTS OF INERT MATRIX-BASED MIXED U-PU FISSILE MATERIAL
		5. SOME CONSIDERATIONS ON INERT MATRICES
		6. DECAY OF 234Pu
		7. CONCLUSIONS
		REFERENCES
	PLUTONIUM DISPOSITIONING IN CANDU
SESSION 5 FUEL PERFORMANCE
	PRACTICES AND TRENDS IN MOX FUEL LICENSING IN FRANCE
		Abstract
		1. CURRENT PROGRAMME OF PLUTONIUM RECYCLING IN THE 900 MWE PWRS
		2. SAFETY REQUIREMENTS RELATED TO THE USE OF MOX FUEL IN PWRS
		3. LICENSING ISSUES RELATED TO THE USE OF MOX FUEL IN PWRS
		4. SHORT TERM AND MID TERM PROSPECTS
		5. LONG-TERM PROSPECTS
	VALIDATION OF MOX FUEL THROUGH RECENT BELGONUCLEAIRE INTERNATIONAL PROGRAMMES
		Abstract
		1. INTRODUCTION
		2. MOX PROGRAMME EXPERIENCE
		3. INTERNATIONAL SUPPORT
		5. CONCLUSIONS
	PLUTONIUM RECYCLING IN FRENCH POWER PLANTS: MOX FUEL IRRADIATION EXPERIENCE AND BEHAVIOUR
		Abstract
		INTRODUCTION
		FUEL DESIGN AND FABRICATION
		R & D PROGRAMME
		ANALYTICAL EXPERIMENTS
		THE SURVEILLANCE PROGRAMMES
		CONCLUSION AND PROSPECTS
		REFERENCES
	MOX FUEL IRRADIATION BEHAVIOUR: RESULTS FROM X-RAY MICROBEAM ANALYSIS
		Abstract
		1. INTRODUCTION
		2. FUEL CHARACTERISATION AND IRRADIATION HISTORY
		3. METHODS
		4. RESULTS
		5. DISCUSSION
		6. SUMMARY AND CONCLUSIONS
		REFERENCES
	BEHAVIOUR OF A DEFECTIVE MOX FUEL ROD IN A PWR
		Abstract
		1. INTRODUCTION
		2. DAMPIERRE UNIT 1 OPERATION DURING CYCLE 11
		3. DAMPIERRE UNIT 1 OPERATION DURING CYCLE 12
		4. ANALYSIS OF ACTIVITY RELEASE DURING CYCLE 12
		5. PRESENTATION OF DEFECTIVE MOX FUEL DISCRIMINATION METHODS DURING PLANT OPERATION
		6. APPLICATION OF DISCRIMINATION METHODS DURING THE 11th AND THE ft CYCLE OF DAMPIERRE UNIT 1
		7. CONCLUSION
		REFERENCES
	IRRADIATION OF ARGENTINE MOX FUELS: POST-IRRADIATION RESULTS AND ANALYSIS
		Abstract
		1. INTRODUCTION
		2. FUEL RODS DESCRIPTION
		3. BU15 EXPERIMENT DESCRIPTION
		4. POSTIRRADIATION EXAMINATIONS OF THE BUI5 EXPERIMENT
		5. BACO CALCULATIONS FOR THE A.1.3 FUEL ROD
		6. CONCLUSIONS
		REFERENCES
	THERMAL AND IN-PILE DENSIFICATION OF MOX FUELS : SOME RECENT RESULTS
		Abstract
		1. INTRODUCTION
		2. IN-PILE DENSIFICATION
		3. EXPERIMENTAL ASPECTS
		4. RESULTS
		5. DISCUSSION
		6. CONCLUSIONS
		REFERENCES
	AECL's EXPERIENCE IN MOX FUEL FABRICATION AND IRRADIATION
		Abstract
		1. INTRODUCTION
		2. MOX FUEL FABRICATION AT AECL
		3. AECL's RECENT IRRADIATION EXPERIENCE (NPD-40)
		4. CURRENT MOX FUEL IRRADIATIONS AT AECL
		5. SUMMARY
		ACKNOWLEDGEMENTS
		REFERENCES
LIST OF PARTICIPANTS
                        

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