Monday, 25 November Tuesday, 26 November Wednesday, 27 November Thursday, 28 November Friday, 29 November

08:30- Registration 08:30- Session 4: Safety of Research Reactors 08:30- Session 3: New Programmes 08:30- Session 4: Safety of Research Reactors 08:30- Session 1: Utilization and Applications 09:30 10:00 Safety Enhancement of Research Reactors – IAEA Programme and 10:00 IAEA Activities in Support of Member States in Establishing Infrastructure 10:00 Safety Review of Research Reactors in , C. Perrin, Argentina 10:00 A Low-Cost High Quality Neutron Computed Tomography System, Activities, A. Shokr, IAEA for New Research Reactor Programme, R. Sharma, IAEA B. Schillinger, 09:30- Conference Opening Periodic Safety Review of Research Reactors: Grading the Scope and Handling Safety of Research Reactors in , F. Nicolas, France Status Report of RA-10 Research Reactor, H. Blaumann, Argentina Extent of Regulatory Review, A. Carpentier, F. Nicolas, France NAA Application in Authenticity and Traceability of Agro-Food Product: 10:00 J.C. Lentijo, IAEA Extended Safety Reassessment of Reactor VR-1 with New National JHR Start-Up Equipments and Experimental Utilities to prepare Periodic Safety and Security Review Plan or the OPAL Reactor, D. Vittorio, Malaysian Rice and Edible Birds’ Nest (EBN), N. Abdullah Salim, J. Gadano, Argentina Nuclear Law, F. Fejt, Czech Republic commissioning, J.-P. Coulon, France Australia Contribution of Neutron Activation Analysis for Nutritional Status The Committee for Evaluation of Experiments a Key to Safety of MTR, Building a Sustainable Research Reactor through Stakeholder Establishment of a PSR Project for ETRR-2, M. Gaheen, Egypt Assessment of Children under Five in Java , M. Santoso, M. Scibetta, Belgium Involvement – the Case of PALLAS, T. Tielens, Netherlands Indonesia Radiobiology in Research Reactor MARIA (Biological Effects of Neutron in Cultured Colon Cancer Cells), M. Gryzinski, Poland

10:00-10:30 Poster Session and Coffee Break

10:00- Session 1: Utilization and Applications 10:30- Session 4: Safety of Research Reactors 10:30- Session 5: Security of Research Reactors 10:30- Session 4: Safety of Research Reactors 10:30- Session 7: Common Management Considerations 11:45 IAEA Activies on Utilization and Application of Research Reactors, 12:15 The Effective Application of the IAEA Code of Conduct on the Safety of 12:15 IAEA Nuclear Security Activities in Support of Research Reactors, D. Shull, 12:15 Leadership and Management for Safety at NRG, J. Offerein, Netherlands 12:15 French Experience in Management of the Interface between Nuclear N. Pessoa Barradas, IAEA Research Reactors in the Regulation of Research and Test Reactors at IAEA PNRA Process for Utilization of Operating Experience Feedback for Safety Safety and Security for Research Reactors, J. C. Niel, France Global Trends in the Use of Medical Radioisotopes and the Vital Role of the U.S.-NRC, Al. Adams, USA Nuclear Security for Research Reactors, K. Mrabit, of Research Reactors in Pakistan, S. Rashid, Pakistan Considerations and Challenges of Research Reactor Management, Research Reactors in Their Production, M. Venkatesh, India Regulatory Supervision and the Status of the Neutron Source Licensing in Enhancing Nuclear Security at the Ghana Research Reactor-1 (GHARR-1) Approaches in Development of PSA for Research Reactors, M. Grinberg, J. Perrotta, Design Strategies for Optimizing the Production of Ir-192 Using the Ukraine, S. Nemtsova, Ukraine Facility of the Ghana Atomic Energy Commission (GAEC), M. Addo, Ghana Argentina Implementation of a Nuclear Knowledge Management Programme on Current Operation Scheme of ETRR-2, N. Mohamed, Egypt Standardization of the Inspection Process for Nuclear Research Reactors Identifying Attractive Targets for Research Reactors and Associated Lessons Learned from the Fukushima Accident – Challenges and Best Decommissioning of Research Reactors, H. Elsayed, Egypt Present Status of UTR-KINKI, G. Wakabayashi, (FORO), G. Lazaro, Peru Facilities – IAEA CRP, A. Sfetsos, Greece Practices in the Safety Improvements for German Research Reactors, Experience with the Management of Heavy Water Research Reactor Pilot Integrated Research Reactor Utilization Review (IRRUR) Mission to Regulations and Safety Aspects of TRIGA 2000 Bandung Reactor Fuel Implementing the Nuclear Security Measures on Nuclear Research K. Niedzwiedz, Germany During the State of Extended Shutdown and Transition Period - Safety LENA TRIGA Mk II: Lessons Learned, A. Salvini, Conversion, A. Awalludin, Indonesia Reactors, M. Mladenovic, Serbia Analytical and Experimental Analysis on Safety Related Aspects of the Considerations, I. Maksimovic, Serbia Hungarian Results in the EU Topical Peer Review of Ageing Management, RMB Research Reactor, A. Belchior Jr, A. C. Santos, Brazil Safety Management and Integrated Management System for Nuclear E. Rétfalvi, Hungary Research Reactors, Used Approach and Experience from Argentina RA-6 Reactor, S. Acuña, Argentina

11:45-13:30 Lunch Break 12:15-13:30 Lunch Break 12:15- Panel Session: Summery Discussion, Conclusions and 13:15 Recommendations 13:30- Session 1: Utilization and Applications 13:30- Session 7: Common Management Considerations 13:30- Session 3: New Research Reactor Programmes 13:30- Session 1: Utilization and Applications 15:00 Strategies for Effective and Sustainable Utilization of Small and Medium 15:00 Management of the Interface Between Nuclear Safety and Security for 15:00 Progress in the MBIR Construction and RIAR’s SM-3 Reactor Core 15:00 Cooperation in Neutron Beam Research in Asia and Pacific Region , Size Research Reactors, K. Unlu, USA Research Reactors – IAEA Approach, A. Shokr, IAEA Refurbishment Project, A. Tuzov, Russia S. Choi, Republic of Korea Internet Reactor Laboratory Project IRL in Argentina, P. Cantero, Argentina Exploring Organizational Governance of Nuclear Security in Research Design Characteristics of LPRR, M. Al Qahtani, Saudi Arabia Enhancing Experimental Capabilities of the Training Reactor VR-1 through 13:15- Closing Session 13:30 Internet Reactor Laboratory Project (IRL): An Effective Collaboration Reactors, T. Le, USA Licensing Experience with the Safety Review and Assessment for Building VR-2 Subcritical Assembly and New Laboratories, L. Sklenka, Young Professional Poster Awards Between CNESTEN and IAEA to Support Nuclear Education in Africa, Implementation of a Graded Approach in the Regulatory System of Construction License for New Research Reactor in Korea, KJRR, S. Kim, Czech Republic N. Mokhtar, Closing Remarks by IAEA C. El Younoussi, Morocco Nuclear Facilities: Challenges and Opportunities, A. Sapozhnikov, Russia Republic of Korea Application of Cold Neutron Sources in Modern Research Reactors, O. Calzetta, Conference Closing Role of Research Reactors as Infrastructure for Nuclear Technology in A Possible Application of the Graded Approach to German Research Feasibility Study for Subcritical Assembly, A. Ben-Ismail, Tunisia G. Sarabia, Argentina Iran, S. Mirvakili, Iran Reactors, M. Trapp, Germany Tests of LWR Fuels at JSC “SSC RIAR”, A. Burukin, Russia

15:00-15:30 Poster Session and Coffee break 13:30- Technical Tour 19:00 15:30- Session 2: Operation and Maintenance 15:30- Session 2: Operation and Maintenance 15:30- Session 6: Fuel Management and Decommissioning 15:30- Session 2: Operation and Maintenance 17:30 IAEA Activities in Support of Operation and Maintenance of Research 17:30 Experience with Modernization of I&C at TRR-1/M1, S. Wetchagarun, 17:30 IAEA Activities Related to the Research Reactor Fuel Cycle, F. Marshall, 17:30 On-Line Monitoring of Systems and Components in Research Reactors, Reactors, R. Sharma, IAEA IAEA P. Sumanth, India Operation and Maintenance of SAFARI-1 Research Reactor: Challenges The Possibilities and Challenge of SPR Under Over-life Operation Spent Fuel Management for Research Reactors: Challenges and The Experience of Ghana in the Core Conversion Project, H. Obeng, and Opportunities in Long Term Operation of Research Reactors, Condition in CIAE, Y. Zhang, China Strategies, P. Ameglio , Australia Ghana J. Du Bruyn, South Africa Modelling of Nuclear Protection System Reliability in the RSG-GAS Spent Fuel Management of the MR and RFT Research Reactors at Stage Deterioration and Replacement of Reactor Water Cleanup System Resin Systematic Approach to The Development of an Operational Ageing Research Reactor, L. Nahari, Indonesia of Preparation for their Decommissioning, S. Semenov, Russia Columns at MURR, B. Meffert, USA Management Programme for the Nigeria Research Reactor-1, Challenges of Operation and Maintenance of Two Research Reactors Regulatory Oversight of Decommissioning of SLOWPOKE-2 Research Comparison Between Coolants Heat Behaviours on Thermal Striping N. Abubakar, Nigeria (Fast Breeder and KAMINI Research Reactor) of Diverse Design, Reactor, I. Erdebil, Canada Phenomenon in New Research Reactor Structures, M. Dougdag, Algeria Operation and Maintenance Experience, Ageing Management and B. Achuthan, India Contribution to IAEA Publication on Research Reactor Spent Fuel Upgrade of the OPAL Reactor Distributed Control System, J. Milthorpe, Challenges & Opportunities of BAEC TRIGA Research Reactor, M. Shohag, Status of Dalat Research Reactor Utilization and a New Research Reactor Management, M. Budu, Australia Project, N.D. Nguyen, Analyses on Project Management Parameters in Decommissioning a Hybrid Method for the Determination of the Average Neutron Flux in a The IEA-R1 62 Years of Operation: Experiences and Lessons Learned, WWR-SM Research Reactor Operation and Maintenance, F.R. Kungurov, Research Reactor, A. Septilarso, Japan Fuel Element of RP-10 and Comparison with Calculated Values Obtained F. Genezini, Brazil Uzbekistan with Serpent Code, A. Zuñiga, Peru Problems of Ensuring the Sustainability of the WWR-M Research Reactor, O. Diakov, Ukraine

17:30- Side Events 1 and 2 17:30- Side Events 3 and 4 18:30 18:30

Side Event 1: Safety Enhancement of Research Reactors Based on the IAEA INSARR Safety Side Event 2: Nuclear Security Enhancement of Research Reactors based on the IAEA Side Event 3: IAEA Peer Review Service – Operation and Maintenance Assessment for Side Event 4: Contribution of International Centres Based on Research Reactors (ICERR) Review Service IPPAS Missions Research Reactors (OMARR) Network to Enhancement of Capacity Building Wednesday, 27 November, 17:30–18:30 Room: Gran Panamericano Wednesday, 27 November, 17:30–18:30 Room: Buenos Aires Thursday, 28 November, 17:30-18:30 Room: Gran Panamericano Thursday, 28 November, 17:30-18:30 Room: Buenos Aires

17:30–17:40 A. Shokr IAEA IAEA INSARR Service and 17:30–17:40 K. Horvath IAEA IAEA IPPAS Missions and Goals R. Sharma IAEA IAEA OMARR Service and 17:30–17:40 F. Marshall IAEA ICERR: Objectives and Scope 17:30–17:40 Overview of its Results Experience P. Marzano Australia G. Bignan France J. Offerein Netherland F.R. Kungurov Uzbekistan M. Addo Ghana A. Tuzov Russian Federation Experience and Benefits with Panel Discussion: IAEA IPPAS Experience and Benefits with Panel Discussion: IAEA IPPAS 17:40–18:00 M. Koenen Netherland 17:40–18:00 M. Shohag Bangladesh IAEA INSARR Missions 17:40–18:10 E. Retfalvi Hungary Missions-Benefits and Lessons IAEA OMARR Mission 17:40–18:00 M. Scibetta Belgium Mission-Benefits and Lessons C. Grant Jamaica Learned J. Pane Indonesia Learned R. Palapa Indonesia H. Vogel USA 18:00–18:25 H. Abou Yehia France Q&A Session 18:00–18:25 R. Sharma IAEA Q&A Session J. L. Castro Peru S. Wu Republic of Korea 18:25–18:30 A. Shokr IAEA Summery and Closing 18:25–18:30 R. Sharma IAEA Summery and Closing 18:10–18:25 K. Horvath IAEA Q&A Session 18:00–18:25 F. Marshall IAEA Q&A Session 18:25–18:30 K. Horvath IAEA Summery and Closing 18:25–18:30 F. Marshall IAEA Summery and Closing 4 3 2 1 Poster Session P.4.22. P.4.21. P.4.20. P.4.19. P.4.18. P.4.17. P.4.16. P.4.15. P.4.14. P.4.13. P.4.12. P.4.11. P.4.10. P.4.09. P.4.08. P.4.07. P.4.06. P.4.05. P.4.04. P.4.03. P.4.02. P.4.01. P.3.14. P.3.13. P.3.12. P.3.11. P.3.10. P.3.09. P.3.08. P.3.07. P.3.06. P.3.05. P.3.04. P.3.03. P.3.02. P.3.01. P.2.09. P.2.08. P.2.07. P.2.06. P.2.05. P.2.04. P.2.03. P.2.02. P.2.01. P.1.25. P.1.24. P.1.23. P.1.22. P.1.21. P.1.20. P.1.19. P.1.18. P.1.17. P.1.16. P.1.15. P.1.14. P.1.13. P.1.12. P.1.11. P.1.10. P.1.09. P.1.08. P.1.07. P.1.06. P.1.05. P.1.04. P.1.03. P.1.02. P.1.01. ID G. Quesada I. Ferrari A. Maître L. Mataloni J. LupianoContreras V. Smirnova L. Bedhesi G. Sarabia H. Graine S. Jonah S. Rashid F. Boschetti A. Maître A. DiBenedetto F. Spadavecchia M. Caputo L. Claramonte E. Beretta P. Ramírez B. Srimok O. Kukhotskyi E. Eisawy C. Niane M. Tufa N. Farjallah J. Ryu R. Pashayev J. Mburu C. Camusso A. dosSantos J. Perrotta G. Arias G. Marinsek R. Ahmed M. Ibrahim T. Amarjargal M. Marticorena Astronomo A. Asuncion- B. Piwowarski C. Humphrey S. Kustituantini A. Horváth H. Adamu A. Giacobone M. Irigaray M. Scibetta X. Wang A. Ancieta A. Johnson L. Cruz F. Bellino M. Nasso M. Febrian C. Sosa A. Arja J. Santisteban V. Fabrizio M. Carta A. Cintas A. Cintas P. Bellino W. Keil A. Salvini U. Bitelli S. Jesus D. Mangiarotti M. Reichenberger J. Longhino P. Delgado M. ChiarvettoPeralta Author Argentina Argentina Argentina Argentina Argentina Russian Federation South Africa Argentina Algeria Nigeria Pakistan Argentina Argentina Argentina Argentina Argentina Argentina Argentina Argentina Thailand Ukraine Egypt Senegal Ethiopia Tunisia Korea, Republicof Azerbaijan Kenya Argentina Brazil Brazil Argentina Argentina Sudan Egypt Mongolia Argentina Poland Australia Indonesia Hungary Nigeria Argentina Argentina Belgium Canada Peru USA Argentina Argentina Argentina Indonesia Argentina Argentina Argentina Italy Italy Argentina Argentina Argentina Argentina Italy Brazil Brazil Argentina USA Argentina Argentina Argentina Country RA-10 RPS QualificationProgram Neutronic andRadiationProtection AnalysisoftheFuelIrradiationFacility BrazilianMultipurposeReactor Performance andSafety AspectsofthePneumaticIrradiationSystem oftheBrazilianMultipurposeReactor Determination ofCritical Variables forThermalModelingofaContainerthe Transportation ofIrradiatedTargets Best EstimatePlusUncertaintycalculationapproach inSafetyAnalysis The Hydrodynamic FormationofTesting SectionsinResearch ReactorUnits Recent DevelopmentsintheOSCAR-5Nodal SolverasAppliedtotheSAFARI-1 Reactor Nuclear Data:From ENDFtoCITVAP CodeforSafetyAnalysis Source Terms forResearch Reactor Safety AssessmentofNIRR-1FacilityafterConversion from HEUTOLEU Regulatory OversightofAgeingManagementforLongTerm OperationofResearch ReactorsinPakistan Validation of INVAP KineticParameterCalculationLine The DesignofthePrimaryNeutron GuideShuttersoftheBrazilianMultipurposeReactor;aMultidisciplinaryChallenge Adaptation oftheSafetyCriteriaforResearch ReactorsinZero PowerReactors-ApplicationfortheRA0Reactor Estimation oftheReactivityParameterinaNuclearResearch Reactor Methodology forResearch Reactors IndividualWorkers RiskEstimation Station BlackoutAnalysisfortheRA-10Reactor Blackout AnalysisfortheRA-1ReactorwithaRELAPModel RA-10 ReactorAssessmentofDefenseinDepthastheBasisforSafetyand LicensingProcess Research Reactor1-Modification 1(TRR-1/M1) Evaluation ofTheMethodologyUsingforandDeterminationProbabilistic InspectionFrequency ofStructures, SystemsandComponentsofThai Thermal HydraulicsVerification SafetyStudiestoSupporttheLicensingofNeutron Source SubcriticalFacility A SafetyAssessmentMethodologyforaDigitalReactorProtection SystemofResearch Reactors Strategic PlanforUtilizationofPlannedResearch ReactorinSenegal Assessment ofNeeds,DevelopmentUserCommunity, StakeholderInvolvementandStrategicPlanningforResearch ReactorinEthiopia Tunisia’s Preliminary SubcriticalAssemblyNeutronic DesignandOptimization Project StatusofKi-JangResearch Reactor(KJRR)with ConstructionPermit Consideration oftheRelevantIssuestoImproving ExistedInfrastructure fortheFirstResearch ReactorConstruction Kenya's PotentialUtilizationofaResearch Reactor RMB DesignObjectives New Plate-Type Core oftheIPEN/MB–01Research ReactorFacilityforValidation ofRMBProject. The RMBProject –Technical andManagementDevelopmentStatus Materials SurveillanceProgram fortheRA10Research Reactor Support totheTraining oftheRA-10Future OperationStaff Through theUtilizationofInteractiveGraphicSimulator Identifying ChallengesofEstablishingaFirstResearch ReactorinSudanbyUsingSelf-AssessmentMethodologyofNationalNuclearInfrastructure On FeasibilityofUsingNitrideFuelinMTRResearch ReactorCore: ComparisonwithU3O8(LEU) Design StudyonResearch ReactorforMongolia RA 6Research ReactorAutomaticConditionMonitoringSystemApplicationsforPredictive Maintenance Utilizing thePhilippineResearch Reactor-1 TRIGAFuelinaSubcriticalAssembly Ageing ManagementofConcrete Structures inMARIAResearch Reactor Optimisation oftheReactorLightWater ChemistryattheOPAL Research Reactor Conceptual DesignoftheBandungResearch ReactorConversion Feasibility toIncrease theExcessReactivityofBMETraining Reactor Conceptual DesignofDataAcquisitionSystemforNIRR-1Maintenance Effect ofPeroxide Hydrogen intheCorrosion ofAA6061AluminumAlloy. Chemical Control fortheLiquidPoisonSystemofFuelElementsIrradiationLoop Possibilities oftheBR2ReactorasaSupportFacilitytoMaterialsandFuelsR&D Reactor PhysicsMethodsforSupportofIrradiationExperimentsintheNationalResearch UniversalReactor(NRU) The BasicDesignofIrradiationBoxfortheProduction Of99MolybdenumonRP10NuclearResearch ReactorUsingResonanceNeutrons Educational UsesoftheMarylandUniversityTraining Reactor Large QuantityProduction ofNewRadioisotopes Experiences inTraining HumanResources UsingEducationalReactorSimulators Validation oftheHydraulicModelsMolybdenumIrradiationRIGSforBrazilianMultipurposeReactor Current DevelopmentStatusofMedicalandIndustrialRadioisotopesProduction Research inTRIGA2000Research ReactorIndonesia Use oftheNuclearReactorRA-0forRemoteTraining ofNuclearReactorStaff Using theRA0NuclearReactorforDevelopinganOpticalAcquisitionSystemUsedinSecondCriticalityApproach oftheEmbalsePowerPlant LAHN: theArgentinean Neutron BeamLaboratoryoftheRA-10Reactor Neutron CharacterizationoftheTAPIRO FastNeutron Source ReactorAftertheRestoringofNominalConfiguration. Experimental CharacterizationoftheNeutron FluxintheTRIGARC-1Reactor. Neutronic EvaluationfortheProductionMedicalRadioisotopesinRA-10Reactor ofAlternative Developing Standard OperationProcedures fortheSiliconDopingIrradiationServiceatRA-10 Estimation ofKineticParametersandPowerCalibrationinSubcriticalConfigurationstheRP-10Reactor A PhysicsRealRemoteLaboratoryPracticalWork UsingtheRA-0NuclearReactor:DesignandImplementation Design, ImplementationandFuture UtilizationofthePGNAAFacilityatUniversityPavia-LENALaboratory Main ExperimentsPerformedintheIPEN/MB-01RRUsingUO2Rodscore R&D, EducationandTraining atTheARGONAUTA RR IRL –ImplementationinLatinAmerica:DevelopmentoftheRA6OnlineSupportPlatform Modernization oftheRadiationMeasurementsModernization LaboratoryattheAdvancedTest ReactorComplex Development andUsageofaDeviceforMixedFieldsDetectorsCharacterization,BasedontheBNCTBeamRA6Reactor Design andValidation ofaProcess SystemfortheRA-10inPoolNeutrography Facility NPP FuelTest FacilityofRA-10Reactor. PowerRampsSimulations,Mock-UpDesignandExperimentalResults Title 7 6 5 4 Poster Session P.7.02. P.7.01. P.6.14. P.6.13. P.6.12. P.6.11. P.6.10. P.6.09. P.6.08. P.6.07. P.6.06. P.6.05. P.6.04. P.6.03. P.6.02. P.6.01. P.5.03. P.5.02. P.5.01. P.4.34. P.4.33. P.4.32. P.4.31. P.4.30. P.4.29. P.4.28. P.4.27. P.4.26. P.4.25. P.4.24. P.4.23. ID International Conference on F. Huet H. Elsayed F. Kungurov M. Gorzala A. Hossen M. Brizuela J. Dickerson,M.Soule A. Talbi H. Park A. ForteGiacobone E. Linardi A. Chesnokov J. Perrotta C. Díaz L. Bak M. Shaat Y. Kilic A. Syuryavin S. Shaban H. AbouYehia Y. Pramono M. Koenen W. Farro G. Caceres Vivanco B. Vilcapaza A. Ancieta A. Cervantes M. Gaheen E. Villarino E. Villarino C. Verrastro Author Research Reactors: Addressing Challenges and Opportunities to France Egypt Uzbekistan Poland Bangladesh Argentina USA France Korea, Republicof Argentina Argentina Russian Federation Brazil Argentina Poland Egypt Indonesia Egypt France Indonesia Netherlands Peru Peru Peru Peru Argentina Egypt Argentina Argentina Argentina Country Ensure Effectiveness and Sustainability

25–29 November 2019, Buenos Aires, Argentina Integrated Management SystemImplementation:KeyFactorsofSuccess BasedonLessonLearned Interaction BetweenNuclear SafetySystemsandSecuritySystemUsing LEU Decommissioning ofIIN-3MPulseResearch ReactorofJSC“Foton”inTashkent Preliminary PlanonDecommissioningofthePolishMARIAResearch Reactor Benchmark CalculationofThermalNeutron FluxofOPAL Research ReactorUsingMonteCarloCodeMCNP5 Radiological SafetyAspectsDuringtheDecommissioning ofaUranylNitrateSolutionIrradiationFacilityatRA6Reactor Proliferation ResistanceOptimizedCores (PRO-Core) Orano Comprehensive SolutionsforResearch ReactorsBack-endOperations Decommissioning Procedure andActivitiesontheRSRforKRR2 Changes inBacterialPopulationsataSpentNuclearFuelFacility Corrosion SurveillanceProgram ofResearch ReactorSpentFuelElementsinInterim Wet StorageFacilitiesinArgentina SNF ManagementoftheMRandRFTResearch ReactorsatStageofPreparation andtheirDecommissioning The RMBProject –FuelCycleManagement Reactor Argentino RA-8:Plan,WithdrawalofServiceandDismantlingtheArgentine ReactorRA-8 Decommissioning ofPolishResearch Reactors–ThePastandFuture A Preliminary Decommissioning PlanforaResearch Reactor Nuclear SecurityofResearch Reactors Evaluation onSecurityChallengesandRisksofIndonesiaRSGGASIWABESSY Research Reactor Challenges FacingNuclearSecurityImplementationatResearch Reactors New IRSNPublicationonResearch Reactors Regulatory AssessmentofSAMOPTest FacilityasUtilizationofKartiniReactor 10-Yearly SafetyEvaluation(10EVA) Operations ExperienceatNRG Accident EvaluationintheTransitional StateinReactorRP-10 Thermo-Hydraulic EvaluationoftheRP-10ReactorUsingFuelAssemblyUraniumSilicideU3Si2. Evaluation oftheNeutronic ManagementoftheRP-10Cores Experimental DeterminationofDelayedNeutron FractionUsingNeutron NoiseandThermalBalanceatRP-10 Signals EmulatorEquipmentDesignforRA-10ofReactorProtection SystemVerification Process Analysis ofSafetyIssuesRelatedtoRestarthighFluxMTRReactorsafterSCRAM INVAP ComputerCodesValidation andMaterialActivation intheFrameofIAEACRPagainstExperimentalDataonFuelBurnup Neutronic andThermalhydraulicUncertaintiesAnalysisinaResearch Reactor Reliability AnalysisforDifferent ConfigurationofaTRIP Final ActuatorInterfaceforSafetySystemofResearch Reactor Title

Organized by the Hosted by the Government of Argentina 19-04888E through the National Atomic Energy Commission (CNEA) CN-277