Accelerator Driven Subcritical Reactors (Series in Fundamental and Applied Nuclear Physics)
By: H. Nifenecker (author), O. Meplon (author), S. David (author)Hardback
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This book describes the basic knowledge in nuclear, neutron, and reactor physics necessary for understanding the principle and implementation of accelerator driven subcritical nuclear reactors (ADSRs), also known as hybrid reactors.Since hybrid reactors may contribute to future nuclear energy production, the book begins with a discussion of the general energy problem. It proceeds by developing the elementary physics of neutron reactors, including the basic nuclear physics involved. The book then presents computational methods, with special emphasis on Monte Carlo methods. It examines the specifics of ADSR, starting from the neutron spallation source to safety features. A thorough discussion is given on the size of hybrid reactors, which follows very different constraints from that of critical reactors. The possibility to optimize the source importance is examined in detail. The discussion of the fuel evolution follows with its relevance to safety and to the waste production and incineration. The conditions for having a constant reactivity over sufficiently long lapse of time are also discussed. The book also evaluates a number of practical designs that have been proposed. Finally, the last chapter deals with the examination of proposed and possible waste transmutation policies and the role which could be played by ADSR in this context. The potential advantage of the Thorium cycle is discussed as well as different scenarios that could be used to implement it.
INTRODUCTIONTHE ENERGY ISSUEWorld Energy PerspectivesRenewable energiesNuclear EnergyCostsThe Possible Role of Accelerator Driven Subcritical ReactorsELEMENTARY REACTOR THEORYInteraction of Neutrons with NucleiNeutron PropagationNeutron Multiplying AssembliesLimiting ValuesReactor ControlFuel EvolutionBasics of Waste TransmutationADSRS PRINCIPLESProperties of the Multiplying MediumPRACTICAL SIMULATION METHODSNeutron Reaction Data FilesDeterministic MethodsMonte-Carlo CodesPhysics in MCNPMCNP in PracticeExamplesFuel evolutionTHE NEUTRON SOURCEInteraction of Protons with MatterAlternative Primary Neutron ProductionExperimental Determination of the Energy GainTwo Stage Neutron MultipliersHigh Intensity AcceleratorsADSR KINETICSREACTIVITY EVOLUTIONSLong Term EvolutionsShort Term Reactivity ExcursionsFUEL REPROCESSING TECHNIQUESBasics of ReprocessingWet ProcessesDry ProcessesGENERIC PROPERTIES OF ADSRSThe Homogeneous Spherical ReactorParametric Study of Heterogeneous SystemsWASTE INCINERATIONThe Thorium-Uranium CycleIncinerationGROUND LAYING PROPOSALSSolid Fuel ReactorsMolten Salt ReactorsCost EstimatesSCENARIOS FOR THE DEVELOPMENT OF ADSRSExperimentsDemonstratorsAPPENDIX A: DEEP UNDERGROUND DISPOSAL OF NUCLEAR WASTEDetermining the Dose to the PopulationAccidental IntrusionHeat Production and Sizing of the Storage SiteGeological HazardAn Underground Laboratory, What For?APPENDIX B: THE CHERNOBYL ACCIDENT AND THE RMBK REACTORSThe RBMK-1000 ReactorEvents leading to the accidentThe accidentAPPENDIX C: BASICS OF ACCELERATOR PHYSICSLinear AcceleratorsCyclotronsSuperconductive solutionsSpace Charge LimitationsINDEX
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- ID: 9780750307437
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