proceedings:2009_igorr12
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| - | ^ Title ^ Author(s) ^ Session ^ Misc ^ | + | ===== October 2009 - Beijing, China ===== |
| - | The Jules Horowitz Reactor: A new European MTR open to International collaboration G.BIGNAN Session 1: New Reactor and General Research Reactor Document | + | |
| - | Research Reactors from Argentine Origin J.P.ORDONEZ Session 1: New Reactor and General Research Reactor Document | + | < |
| - | Future of French Design and Construction Code for Research Reactors C.PASCAL; B.DRUBAY Session 1: New Reactor and General Research Reactor Document Full paper | + | ^ Title |
| - | Implementation of Molybdenum Production in Polish Research Reactor MARIA A.GOLAB Session 10: Research Reactor Utilization II Document | + | | {{ :proceedings:2009_igorr12:igorr_2009_presentation.pdf |Opening Lecture « Nuclear Renaissance and the key role of Research Reactors »}} |
| - | Thermal Assessment of the CALIPSO Irradiation Device for the Jules Horowitz Reactor D.MOULIN Session 10: Research Reactor Utilization II Document Full paper | + | | {{ : |
| - | The MADISON Experimental Hosting System in the Future Jules Horowitz Reactor P.ROUX Session 10: Research Reactor Utilization II Document Full paper | + | | {{ : |
| - | Reactivity Challenges of the EVITA Irradiation Program at BR2 E.KOONEN Session 10: Research Reactor Utilization II Document | + | | {{ : |
| - | Conducting a State Systems of Accounting for and Control of Nuclear Materials Training Program L.P. FOYTO Session 10: Research Reactor Utilization II Document | + | | {{ : |
| - | Refurbishment and Upgrade of ILL Reactor and Instrument Suite H.J GUYON Session 3: Research Reactor Modifications Document | + | | {{ : |
| - | Neutron Commissioning in the CABRI Water Loop Facility G.RITTER Session 3: Research Reactor Modifications Document Full paper | + | | {{ : |
| - | Design and Construction of a Zircaloy Pressure Vessel for the Research Reactor CABRI D.BOURGUIGNON Session 3: Research Reactor Modifications Document Full paper | + | | {{ : |
| - | PROTEUS Upgrade – Modernization and Refurbishment of the PROTEUS Facility G.PERRET Session 3: Research Reactor Modifications Document | + | | {{ : |
| - | NRU Reactor Vessel Repair G.B WILKIN Session 3: Research Reactor Modifications Document | + | | {{ : |
| - | Annular Core Research Reactor Improved Pulse Repeatability/ | + | | {{ : |
| - | Annular Core Research Reactor Pneumatic Transfer System Design T.Q TRINH Session 4: Operating Reactors and Critical Facilities Document | + | | {{ : |
| - | CARMEN: An Experimental Configuration in the MINERVE Critical Facility for the Qualification of Neutron Cross Sections in an Epithermal Spectrum J. DI SALVO Session 4: Operating Reactors and Critical Facilities Document Full paper | + | | {{ : |
| - | LIFE @ PROTEUS Experimental Program G.PERRET Session 4: Operating Reactors and Critical Facilities Document | + | | {{ : |
| - | Jules Horowitz I&C Overview L.RODRIGUEZ Session 5: Instrumentation and Control Document Full paper | + | | {{ : |
| - | Performance Indicators for Research Reactors G.STORR Session 6: Operations and Maintenance Document | + | | {{ : |
| - | Configuration Control and Implementation of Safety Principles on the Research Side of the HFIR Site Operations D.SELBY Session 6: Operations and Maintenance Document | + | | {{ : |
| - | OPAL Reflector Vessel – Repairs Options to Mitigate Light Water Leaks R.THIERING Session 6: Operations and Maintenance Document | + | | {{ : |
| - | OPAL Engineering Early Modifications Relating to DBA Loss of Offsite Power (LOOP) P.METCALF Session 7: Research Reactor Safety Document | + | | {{ : |
| - | Reactivity Insertions for the Borax Accident in ORPHEE Reactor Y.CHEGRANI Session 7: Research Reactor Safety Document | + | | {{ : |
| - | Safety and Reliability Improvements in OSIRIS G.BIGNAN Session 7: Research Reactor Safety Document | + | | {{ : |
| - | Overcoming Challenges in the ZED-2 Reactor Safety Analysis G.B WILKIN Session 7: Research Reactor Safety Document | + | | {{ : |
| - | Status of Cold Neutron Research Facility Installation in HANARO I.C LIM Session 8: Secondary Sources Document | + | | {{ : |
| - | Maintenance, | + | | {{ : |
| - | The Ultra-Cold Neutron Laboratory at the FRM-II A.FREI Session 8: Secondary Sources Document | + | | {{ : |
| - | he JHR MOLY System: Towards a Concept Proposal According a Large Molydenum Production Capabilities S.GAILLOT Session 9: Research Reactor Utilization I Document Full paper | + | | {{ : |
| - | Non Destructive Examination Benches and Analysis Laboratories in Support to the Experimental Process in the Jules Horowitz Reactor D.P PARRAT Session 9: Research Reactor Utilization I Document Full paper | + | | {{ : |
| - | The IAEA Activities in Support of Research Reactor Utilization and Applications D.RIDIKAS Special Plenary Session Document | + | | {{ : |
| - | Towards the Renewal of the European Research Area of Experimental Reactors: The MYRRHA Project P.BAETAN Welcoming session Document | + | | {{ : |
| - | Opening Lecture « Nuclear Renaissance and the key role of Research Reactors » J.GUIDEZ 0 - General Session Document | + | | {{ : |
| - | The new Research Reactors of CIAE: CARR and CEFR PR. Y.LUZHENG; DR. S. FENG 0 - General Session Document | + | | {{ : |
| - | The Advanced Test Reactor National Scientific User Facility Mitchell K. Meyer, Todd Allen, Frances M. Marshall, Jeff B. Benson, Mary C. Thelen 0 - General Session Document The Advanced Test Reactor National Scientific User Facility | + | | {{ : |
| - | Sustaining Material Testing Capacity in France : From OSIRIS to JHR G. Bignan, D. Iracane, S. Loubière, C. Blandin 0 - General Session Document Sustaining Material Testing Capacity in France:From OSIRIS to JHR | + | | {{ : |
| - | Australia’s new Research Reactor-OPAL G.J. Storr 0 - General Session Document OPAL: | + | | {{ : |
| - | Refurbishment Status and Future Program of Japan Material Testing Reactor JMTR M. Ishihara, H. Kawamura, M. Niimi, N. Hori, Y.Nagao 0 - General Session Document Refurbishment Status and Future Program of Japan Material Testing Reactor JMTR | + | | {{ : |
| - | Current Status of HANARO and Future Plan In-Cheol LIM, | + | | {{ : |
| - | The High Flux Isotope Reactor: Past, Present and Future Kelly Beierschmitt 0 - General Session Document History of HFIR | + | | {{ : |
| - | Developments of Irradiation Facilities for Research And Medical Isotope Production in Petten A.M. Versteegh, B. van der Shaaf 0 - General Session Document Developments of Irradiation Facilities for Research And Medical Isotope Production in Petten | + | | {{ : |
| - | The BR2 Reactor: the challenges for continuous operation Way into the 21st E.Koonen 0 - General Session Document The BR2 Reactor: the challenges for continuous operation Way into the 21st | + | | {{ : |
| - | Fast Reactor Technology facing nuclear Energy Sustainable development in China Donghui Zhang 0 - General Session Document | + | | {{ : |
| - | Experimental Research Reactor LVR15 : Present status and Programs J. Kysela, J.Prahl 0 - General Session Document Experimental Research Reactor LVR15 : Present status and Programs | + | | {{ : |
| - | IAEA’s Subprogramme on Research Reactors P. Adelfang 0 - General Session Document | + | | {{ : |
| - | Multiple purpose research reactors for the 21st century W. Petry 0 - General Session Document | + | | {{ : |
| - | Present Status and Future Plans of the Halden Reactor M. A. McGrath 0 - General Session Document | + | | {{ : |
| - | Research Reactors at the French Atomic Energy. Commission: Past, present and future P. Raymond 1 - New Project and General Strategy Document Research Reactors | + | | {{ : |
| - | The current status of neutrons scattering facilities at CARR Yuntao Liu 1 - New Project and General Strategy Document | + | | {{ : |
| - | Irradiation effects on 6061-T6 Aluminium alloy used for JHR Internal Structures B. Kapusta, J. Garnier, B. Maugard, L. Allais, P. Lemoine 1 - New Project and General Strategy Document Irradiation effects on 6061-T6 Aluminium alloy used for JHR Internal Structures | + | </datatables> |
| - | The progress of CARR’s neutron image facilities Hongli Wang 1 - New Project and General Strategy Document | + | |
| - | Irradiation Facilities and examination Benches For implementing fuels programs in the future JHR Material Testing Reactor D. Parrat, M. Tourasse, C. Gonnier, S. Gaillot, P. Roux 1 - New Project and General Strategy Document Presentation | + | |
| - | Fundamental research on Molten Salt Reactors Dalin Zhang 1 - New Project and General Strategy Document Presentation | + | |
| - | The ADELINE irradiation loop in the JHR MTR : Testing a LWR fuel rod up to the limits with a High quality level experimental process S. Gaillot, D.Parrat, G.Laffont, C.Garnier, C.Gonnier 1 - New Project and General Strategy Document Presentation | + | |
| - | Underwater NDE Systems in the JHR : Towards integration issues G. Le Guillou, B. Berthet, S. Gaillot 1 - New Project and General Strategy Document Presentation | + | |
| - | Numerical Analysis of Flow and Heat Transfer in a Fuel Subassembly of SFRs with Porous Model Yizhe Liu 1 - New Project and General Strategy Document | + | |
| - | AMMON: An experimental program in the EOLE Critical facility for the validation of the JHR Neutron and photon HORUS3D calculation scheme JC. Bosq, JC. Klein, N. Thiollay, J. Di Salvo, G. Bignan, P. Sireta, JP Wieryszkov, | + | |
| - | Design study of a small long life fast reactor core loaded with Pu without extracting MA Yun Hu, Mi Xu 1 - New Project and General Strategy Document Presentation | + | |
| - | Studies of Past Operations at the High Flux Isotope Reactor R.T. Primm, D. Chandler 2 - Enrichment Conversion Document Presentation | + | |
| - | OPAL Commissioning and Early Operation : A Shift Manager’s perspective CK. Teoh 3 - Research Reactor Operation and Improvement Document Presentation | + | |
| - | The Safety Review and Update of the Safety Analysis Report for the OPAL Reactor M.W. Summerfield 3 - Research Reactor Operation and Improvement Document Presentation | + | |
| - | OPAL Cold Neutron Source Heat Load Measurement Weijian LU 3 - Research Reactor Operation and Improvement Document Presentation | + | |
| - | A second Liquid Hydrogen Cold Source for the NIST Research Reactor R.E. Williams, M. Middleton, P.Kopetka, J.M.Rowe 3 - Research Reactor Operation and Improvement Document Presentation | + | |
| - | Advanced Test Reactor and Experiment Research Program F.M. Marshall, S. Blaine Grover 3 - Research Reactor Operation and Improvement Document Presentation | + | |
| - | Current Status of the Spent Fuel Management in HANARO Mun.Lee, | + | |
| - | Development and manufacturing of special Fission chambers for in-core measurement Requirements in nuclear reactor B.Geslot (presented by Dr Bignan) , S. Breaud, C. Jammes, P. Filliatre, JF. Villard,. Berhouet 3 - Research Reactor Operation and Improvement Document Presentation | + | |
| - | MERCI-MOSAIC: | + | |
| - | Present Status of Operation and Maintenance of JRR-3 T.Ichimura, | + | |
| - | Some essential features of the TAPIRO Fast-Neutron Source Reactor located at ENEA-CRE Casaccia R. Rosa, | + | |
| - | How can the availability of safe and secure Research reactors be assured in future? | + | |
| - | Questioning the Self-Protection of Nuclear Materials At Research Reactors around the world F.Dalnoki Veress 4 - Generalities Document | + | |
| - | The MADERE radio-activity measurement Platform: Developments for a better address of the experimental needs J.M. Girard (presented by Dr Bosq), H. Philibert, | + | |
| - | Commissioning Test Program in CABRI after The Refurbishment of the Reactor and the implementation Of a Pressurized Water Loop J. Estrade 5 - Research Reactors Refurbishment Document Presentation | + | |
| - | Neutronic characterization and safety assessment Of CABRI core O.Gueton, | + | |
| - | Building a new safety case for the nuclear core of CABRI G. Ritter (presented by J.Estrade), F. Jeury 5 - Research Reactors Refurbishment Document Presentation | + | |
| - | Analysis of CABRI driver core new safety demonstration For fuel rods integrity during fast power transients F. Ecrabet, C. Pelissou 5 - Research Reactors Refurbishment Document Presentation | + | |
| - | Validation and qualification of the ANUBIS scheme, Used for safety assessment and operation management Of the OSIRIS reactor O.Gueton, | + | |
| - | Fuel Rod Instrumentation Techniques implemented In CEA hot Laboratory: Improvement and Experimental feed-back F. Berdoula, | + | |
| - | A Core Pressure Drop Monitoring System: Design and implementation at the RA6 Research Reactor F. Brollo Document | + | |
| - | Adaptation of ANUBIS scheme to SAFARI-1 core characterisation L. Moloko Document | + | |
| - | ADVANCE IN THE RA-10 REACTOR PROJECT H. Blaumann Document | + | |
| - | Ageing Management Programme for Research Reactors in Argentina G. Vega Document | + | |
| - | Ageing Management, Obsolescence and Refurbishment of GHARR-1 Structures, Systems and Components (SSCs) E.O. Amponsah-Abu Document | + | |
| - | ANALYSIS OF A CORE COOLING FLOW BYPASS EVENT PRODUCED BY SPURIOUS OPENING OF A FLAP VALVE AT THE PRIMARY COOLING CIRCUIT OF THE RA-10 REACTOR R. Hilal Document | + | |
| - | Analysis of a Loss of Offsite Power Event for the RA-10 Reactor S. Papadakis Document | + | |
| - | Analysis of an Inadvertent Control Plate Withdrawal Event in the RA-10 Reactor R. Maturana Document | + | |
| - | Analysis on LCO for On-Power Loading/ | + | |
| - | CFD Models of the RA-10 RI Facilities: A Useful Tool for Design Support M. Gramajo Document | + | |
| - | Characterization of UO2-Gd2O3 nuclear fuel obtained by co-precipitation by Transmission Electron Microscopy I. Gana Document | + | |
| - | CNEA DEVELOPMENTS IN U-Mo-Zry-4 MINIPLATES AND PLATES CO-ROLLING CONTROL B. Picchetti Document | + | |
| - | COCONEUT: An innovative deterministic neutronic calculation tool for research reactors J.-G. Lacombe Document | + | |
| - | Conceptual Design of a Compact Nuclear Reactor Core R.Vignolo Document | + | |
| - | Conceptual Design of a Research Reactor with Monolithic UMo Fuels J.I. Beliera Document | + | |
| - | Conceptual Design of the Core of an ADS (Accelerator Driven System) M. Tacca Document | + | |
| - | Contributions of CFD to the analysis of the second shutdown system of the RA-10 research reactor L. M. Rechiman Document | + | |
| - | Correction factors to apply to fission rates measured by miniature fission chambers in various neutron spectra B. Geslot Document | + | |
| - | Creativity in Cold Neutron Sources Design L. Manifacier Document | + | |
| - | CURRENT STATUS OF JRR-3 Y. Kashima Document | + | |
| - | Current Status of the KJRR Project and its Design Features C.Park Document | + | |
| - | Cyber Security Study for Research Reactors J. Shin Document | + | |
| - | Density determination of pyrotechnical devices using neutron imaging techniques on the RA-6 reactor N. Chiaraviglio Document | + | |
| - | DEPLETION ANALYSIS OF THE OPAL REACTOR WITH VESTA P.Young Document | + | |
| - | Description and Applications of the Neutron Imaging Facility at RA-6 J. Marin Document | + | |
| - | Design and first operation of the DIAMINO (U241AmO2) experiment in OSIRIS MTR for Am-recycling program S. BENDOTTI, C. NEYROUD, S. BEJAOUI, T. LAMBERT Document | + | |
| - | Design of a calibration beam for detector characterization J. M. Longhino Document | + | |
| - | Development of Emergency Operating Guidelines for a Research Reactor Hyeonil Kim Document | + | |
| - | Development of Equipment for Simulating Coolant Flow in a Test Rig J. T. Hong Document | + | |
| - | Development of Laser Welding Technology for Fabricating Nuclear Fuel Test Rig C.Y. Joung Document | + | |
| - | Development of Safety Management Portal System for HANARO Research Reactor Hoan Sung Jung Document | + | |
| - | Deviation from ASME III Code rules for the design of Research Reactors M. Wesley Document | + | |
| - | Diving in the pool of a Research Reactor Inspection of the natural convection valves of the primary circuit of OSIRIS reactor during summer outage J.S. Zampa Document | + | |
| - | Dog-Bone Studies In U-Mo-Zry-4 Miniplates Fabrication Process M. Lopez Document | + | |
| - | Education and Training at Low Power Research Reactor VR-1 for National and International Students and Trainees Lubomir Sklenka - Czech Republic Document | + | |
| - | ENEA Thermal and Fast Research Reactors utilization for R&D activities at Casaccia Center M. Sepielli Document | + | |
| - | Expansion of the Cold Neutron Facilities and Reactor Upgrades at the NIST Center for Neutron Research R. E. Williams Document | + | |
| - | Experimental Investigation of Operational Parameters in the CDTN TRIGA Reactor A.Z Mesquita Document | + | |
| - | Experimental Study on Downward Two-Phase Flow in Vertical Narrow Rectangular Channel J.H. Jeong Document | + | |
| - | FPGA Based Reactor Protection System Architecture C.A. Verrastro Document | + | |
| - | FRM II: Results and experience of the major maintenance shutdown after ten years of operation A. Pichlmaier Document | + | |
| - | Heat Deposition in Out-Core Devices of Research Reactors after Actuation of a Shutdown System Based on Reflector Tank Draining H. Meier Document | + | |
| - | High Order Finite Elements for Reactor Calculation. Examples and Comparison with Experimental Results Carlos R. Grant Document | + | |
| - | Implementation and Utilization of Positron Annihilation Spectrometry Methods at the PULSTAR Reactor A. I. Hawari Document | + | |
| - | Implementation of a Periodic Safety Review of HANARO Research Reactor Minjin Kim Document | + | |
| - | Implementation of the Neutron Noise Technique for Measurement of Reactivity in Subcritical of the Low Power Research Reactor RA-4 J. Orso Document | + | |
| - | IMPROVING IMMUNITY OF THE OPAL REACTOR TO ELECTRICAL POWER DISTURBANCES B. GITTOES Document | + | |
| - | Instrumentation & Control Systems for the Brazilian Multipurpose Reactor - RMB P. Carvalho Document | + | |
| - | Integral (n,y) Cross-sections Measurement of Standard Light Water Reactors Materials A. Gruel Document | + | |
| - | Investigation of Mixed Enrichment Core Loadings for the PULSTAR Reactor A. I. Hawari Document | + | |
| - | IRRADIATION CAPSULE DESIGN TO SUPPORT DOE RESUMPTION OF US 60Co ISOTOPE PRODUCTION R. Howard Document | + | |
| - | Irradiation Facilities Performance at RA-10 F. Sanchez Document | + | |
| - | Irradiation Loop Facility in RA-10 Reactor L. Vazquez Document | + | |
| - | Irradiation Requirements for Radioisotope Production D. Hergenreder Document | + | |
| - | JULES HOROWITZ REACTOR OPERATION IN MOCK-UP MODES J. Estrade Document | + | |
| - | Jules Horowitz Reactor: organization for the preparation of the commissioning phase and normal operation J. Estrade Document | + | |
| - | Kinetic Parameters Estimation in the RA-0 Research Reactor P. Bellino Document | + | |
| - | LEVEL 1 PROBABILISTIC SAFETY ASSESSMENT FOR LICENSING OF RA-10 REACTOR M. Grinberg Document | + | |
| - | LEVEL 2 AND 3 PROBABILISTIC SAFETY ASSESSMENT FOR LICENSING OF RA-10 REACTOR C. Mulleady Document | + | |
| - | LORELEI: A future Test Device for LOCA Experiments in the JHR L. Ferry Document | + | |
| - | Materials Surveillance Programme for the RA10 Research Reactor R. Versaci Document | + | |
| - | Measurement of Fission Products and Chemical Species released by Experimental Samples irradiated in the Jules Horowitz Reactor D. Parrat Document | + | |
| - | Measurement of the Xenon-135 Reactivity Evolution after a Shutdown in the RA-3 Research and Production Reactor P. Bellino Document | + | |
| - | Mechanicals description of RA-10 Reactor and Service Pool and main Core Components A. Coleff Document | + | |
| - | More than Forty Years of Neutronics Experiments in Critical Facilities of Cadarache Center: From EOLE and MINERVE to the Future ZEPHYR Reactor S. Cathalau Document | + | |
| - | Neutron Absorbing Glass Microspheres as Second Shutdown System I. Gana Document | + | |
| - | Neutron and Gamma Shielding Design of the Neutron Guide Primary Shutter in a Research Reactor A. Maître Document | + | |
| - | Neutron Cold Source Optimization for RA-10 reactor A. Marquez Document | + | |
| - | Neutron Flux and Reactor Kinetic parameters Calculations in the RA0 Reactor L. Romero Document | + | |
| - | Neutronic Analysis of the Jamaican SLOWPOKE-2 Research Reactor for the Conversion from HEU to LEU Fuel H. Dennis Document | + | |
| - | Neutronic Calculation Methodology for Research Reactors E. Villarino Document | + | |
| - | Neutronic Design of the RA10 Research Reactor´s Core J.M.Tunon Document | + | |
| - | Neutronic Design of the RMB Research Reactor J.M.Tunon Document | + | |
| - | Neutronic Simulation of IPR-R1 TRIGA First Configuration using Serpent and MCNP Codes S. P. de Meireles Document | + | |
| - | New Core with Low-Enriched Uranium Fuel at the Kazakhstan Critical Facility A. Shaimerdenov Document | + | |
| - | Nuclear Education & Training activity experience at the University of Pavia A. Salvini Document | + | |
| - | Nuclear Instrumentation System of RA-10 G. Quesada Document | + | |
| - | Numerical Investigation of Cooling in the Pool of the Brazilian Multipurpose Reactor (RMB) A.Z Mesquita Document | + | |
| - | OPAL Reactor Full 3-D Calculations using the MonteCarlo Code Serpent 2 Diego Ferraro Document | + | |
| - | Operation and Utilisation of Low Power Research Reactor Critical Facility for Advanced Heavy Water Reactor (AHWR) S. K. De Document | + | |
| - | OPERATION, MAINTENANCE EXPERIENCE AND FUTURE CHALLENGES OF TRIGA RESEARCH REACTOR OF BANGLADESH M. A. Salam Document | + | |
| - | Optimisation Approach to Asses Seismic Reinforcements of a Low Power Research Reactor M. Auzas Document | + | |
| - | PARCS Few-group Homogenized Parameters Generation using Serpent Monte Carlo code at the CROCUS Reactor A. Rais Document | + | |
| - | Preliminary Studies on A New Research Reactor and Cold Neutron Source at NIST Zeyun Wu Document | + | |
| - | Preparation and Submission of a Manuscript for the Proceedings of the Technical Meeting A. Malaquias Document | + | |
| - | Production Facilities for Reactor Produced Radioisotopes J. Merino Document | + | |
| - | RA10 - Utilization-driven Layout N. De Lorenzo Document | + | |
| - | RA-10 Design Management: Strategic Objectives and Specific Actions F. Brollo Document | + | |
| - | RA-10 Project Safety Assessment and Licensing Process P. Ramirez Document | + | |
| - | Relevant Characteristics of the RA-10 I&C Systems P. Cantero Document | + | |
| - | Relicensing of the SM1 Sub-critical assembly of the Pavia University L. Strada Document | + | |
| - | Renovation, | + | |
| - | Replacement of the Oregon State University TRIGA® Reactor Annular Reflector S. Todd Keller Document | + | |
| - | Research Institute of Atomic Reactors D. Fomin Document | + | |
| - | Research Reactor Spent Fuel Management in Argentina L. Mottillo Document | + | |
| - | Review of low-power research reactor developed for education and training In-Cheol Lim - Korea Document | + | |
| - | RMB: THE NEW BRAZILIAN MULTIPURPOSE RESEARCH REACTOR J.A. Perrotta Document | + | |
| - | Simplified Method For Thermal-Hydraulic Design And Evaluation Of Research Reactor Core, Coupled With Neutronic Montecarlo Calculation M.A.N Giménez Document | + | |
| - | SIREx: Instrumentation System for Research Reactors F.D. Rossi Mescolatti Document | + | |
| - | Start-up of a New Storage Facility for Spent Fuel from Research Reactors at CNEA O. Novara Document | + | |
| - | Status of uranium targets irradiation in MARIA reactor for molybdenum production G. Krzysztoszek Document | + | |
| - | The Enhancement of VR-1 Reactor Utilization for Practical Education Using Portable Neutron Generator J. Rataj Document | + | |
| - | The IPEN/MB-01 zero power reactor and the LABGENE reactor experimental programme P. Piovezan Document | + | |
| - | The Jules Horowitz Reactor: A new high performance MTR (Material Testing Reactor) working as an International User Facility in support to Nuclear Industry, Public Bodies and Research Institutes G. Bignan Document | + | |
| - | The RMB Research Reactor Project C. Mazufri Document | + | |
| - | Thermal-Hydraulic Aspects for the Upgrade of a Research Reactor C. Pavon Document | + | |
| - | Thermal-hydraulic aspects of RMB design J. Lupiano Contreras Document | + | |
| - | TRACE Code Application to Low Operating Pressure Research Reactor Safety Analysis A. Rais Document | + | |
| - | Trace element Content of Zingiber Officinalis and Salvia Officinalis plants from Algeria Z.Lamari Document | + | |
| - | Transmutation Experimental Facility for Research and Development of Accelerator-Driven System in JAEA K. Tsujimoto Document | + | |
| - | Use of Pulse-Mode Neutron Flux-Change-Rate as a Trip Condition in a Nuclear Reactor F.N. Ferrucci Document | + | |
| - | Use Virtual Environments for Training in Nuclear Facilities P. Carvalho Document | + | |
| - | Utilization of the Dalat Research Reactor After Its Core Conversion N. Nhi Dien Document | + | |
| - | Utilization of the High Flux Isotope Reactor at Oak Ridge National Laboratory D. L. Selby Document | + | |
| - | Utilization, | + | |
| - | Wide Range Amplifier for Neutron Flux Measurement L. Giuliodori Document | + | |
| - | Refurbishment and Activities at Tajoura Reactor Feisal Abutweirat, Mohammed Busitta 1 - International Topics and Overview on New Projects and Fuel Developments Document | + | |
| - | Outlook on France’s R&D Strategy on Future Nuclear Systems Frank Carré, Claude Renault, Pascal Anzieu, Philippe Brossard, Pascal Yvon 1 - International Topics and Overview on New Projects and Fuel Developments Document | + | |
| - | Developing Research Reactor Coalitions and Centres of Excellence Ira N. Goldman, Pablo Adelfang, Arnaud Atger, Kevin Alldred, Nigel Mote 1 - International Topics and Overview on New Projects and Fuel Developments Document | + | |
| - | Irradiation Facilities at the Advanced Test Reactor S. Blaine Grover 1 - International Topics and Overview on New Projects and Fuel Developments Document | + | |
| - | The Renaissance of Sodium Fast Reactors Status and Contribution of Phenix J. Guidez 1 - International Topics and Overview on New Projects and Fuel Developments Document | + | |
| - | Reducing the Risk of Nuclear Terrorism through the Creation of a New Forum for Collecting and Sharing Nuclear Material Security Best Practices: | + | |
| - | JHR Project Status Daniel Iracane 1 - International Topics and Overview on New Projects and Fuel Developments Document | + | |
| - | Current and Prospective Fuel Test Programmes in the Mir Reactor A.L. Izhutov, A.V. Burukin, S.A. Iljenko, V.A. Ovchinnikov, | + | |
| - | The Characteristics of Carr Design and Status of the Project Yuan Luzheng, Ke Guotu, Jin Huajin 1 - International Topics and Overview on New Projects and Fuel Developments Document | + | |
| - | The Opal Reactor R. Miller, T. Irwin 1 - International Topics and Overview on New Projects and Fuel Developments Document | + | |
| - | Operational Safety, Regulatory Requirements, | + | |
| - | Status of Modernization and Refurbishment (M&R) Activities of the IRT - Research Reactor - Sofia/ | + | |
| - | Status of the High Flux Isotope Reactor and the Reactor Scientific Upgrades Program Douglas Selby 2 - New Projects and Upgrades Document | + | |
| - | Conceptual Design of a Pressurized Water Loop for the Irradiation of 6 Fuel Rods in the Jules Horowitz Reactor D. Moulin, B. Pouchin, D. Parrat, N. Schmidt 2 - New Projects and Upgrades Document | + | |
| - | New Moderator Chamber of the FRG-1 Cold Neutron Source for the Increase of Cold Neutron Flux P. Schreiner, W. Knop, D. Coors, D. Vanvor 2 - New Projects and Upgrades Document | + | |
| - | Development of High Temperature Capsule for RIA-Simulating Experiment with High Burnup Fuel Toshiyuki Suzuki, Miki Umeda 2 - New Projects and Upgrades Document | + | |
| - | New Silicon Irradiation Rig Design for Opal Reactor Peter Amos 4 - Optimisation and Research Reactor Utilisation Document | + | |
| - | Residual Heat Estimation by Image Processing Using Cherenkov Radiation in TRR M. Arkani, M. Gharib 4 - Optimisation and Research Reactor Utilisation Document | + | |
| - | Materials Surveillance Program for the Opal Research Reactor Bob Harrison 4 - Optimisation and Research Reactor Utilisation Document | + | |
| - | Vibration Monitoring and Diagnostic of the IEA-R1 Nuclear Research Reactor Erion de Lima Benevenuti, Daniel Kao Sun Ting 4 - Optimisation and Research Reactor Utilisation Document | + | |
| - | Measurement of Void Fraction in Hydrogen Moderator Used for Moderator Cell of Hanaro Cold Neutron Source Myong-Seop Kim, Jungwoon Choi, Young-Chil Kim, Dong-Gil Hwang, Sang-Beom Hong, Kye-Hong Lee 4 - Optimisation and Research Reactor Utilisation Document | + | |
| - | Status of the High Flux Isotope Reactor Cold Source Project Ken Morgan, Douglas Selby 4 - Optimisation and Research Reactor Utilisation Document | + | |
| - | Overview of the IAEA Activities on Safety of Research Reactors A.M. Shokr 4 - Optimisation and Research Reactor Utilisation Document | + | |
| - | Optimization of the Poolside Facility for Neutron Doping of Silicon in High Flux Materials Testing Reactor BR2 V. Kuzminov, H. Blowfield 5 - Innovative Methods in research Reactor Physics Document | + | |
| - | Determining MTR RIA Limits Using Experimental Data Simon E. Day 5 - Innovative Methods in research Reactor Physics Document | + | |
| - | Neutronic Analysis for Conversion of the Ghana Research Reactor-1 Facility Using Monte Carlo Methods and UO2 LEU Fuel S. Anim-Shampong 6 - Safety, Operation and Research Reactor Conversion Document | + | |
| - | Identification of a Leakinf Triga Fuel Element at the Nuclear Research Reactor Facility of the University of Pavia A. Borio Di Tigliole, M. Cagnazzo, F. Lana, A. Losi, G. Magrotti, S. Manera, F. Marchetti, P. Pappalrdo, A. Salvini, G. Vinciguerra 6 - Safety, Operation and Research Reactor Conversion Document | + | |
| - | Results of 14MW Research Reactor Core Conversion Measured at Low Power M. Ciocanescu, M. Preda, C. Toma, G. Negut, D. Barbos, C. Iorgulis, M. Parvan 6 - Safety, Operation and Research Reactor Conversion Document | + | |
| - | Radiation Protection Design of the FRM II Wolfgang Dittrich, Helmut Zeising 6 - Safety, Operation and Research Reactor Conversion Document | + | |
| - | Neutronic Calculations for Conversion of One-Element Cores from HEU to LEU Using Monolithic Umo Fuel Matthias Englert, Wolfgang Liebert 6 - Safety, Operation and Research Reactor Conversion Document | + | |
| - | JRR-3 Maintenance Program Utilizing Accumulated Operational Data Hironobu Izumo, Tomoaki Kato, Masami Kinase, Yoshiya Torii, Yoji Murayama 6 - Safety, Operation and Research Reactor Conversion Document | + | |
| - | Fuel Manufacture in South Africa : the Road to Conversion, a Partnership Nesca and Areva Cerca A. Kocher, RW. Jamie 6 - Safety, Operation and Research Reactor Conversion Document (Part 1) Document (Part 2) | + | |
| - | The Dalat Nuclear Research Reactor Operation and Conversion Study Status Pham Vam Lam, Nguyen Nhi Dien, Luong Ba Vien, Le Vinh Vinh, Huynh Ton Nghiem, Nguyen Kien Cuong 6 - Safety, Operation and Research Reactor Conversion Document | + | |
| - | Safari-1 : Adjusting Priorities During the LEU Conversion Program C. Piani 6 - Safety, Operation and Research Reactor Conversion Document | + | |
| - | Analysis of an LEU Fuel with Spatially Dependent Thickness in Two Dimensions R.T. Primm, R.J Ellis 6 - Safety, Operation and Research Reactor Conversion Document | + | |
| - | Conversion of Research and Test Reactors : Status and Current Plans Parrish Staples, Nicholas Butler, Jordi Roglans 6 - Safety, Operation and Research Reactor Conversion Document | + | |
| - | U.S. Domestic Reactor Conversion Programs Dana Meyer, Eric Woolstenhulme 6 - Safety, Operation and Research Reactor Conversion Document | + | |
| - | Application of Best Estimate Thermalhydraulic Codes for the Safety Analysis of Research Reactors M. Adorni, A. Bousbia Salah, F. D' | + | |
| - | Sophisticated MCNP Calculation of the Flux Map of FRJ-2 using a fully nodalized Model P. Bourauel, R. Nabbi 5 - Innovative Methods in research Reactor Physics Document | + | |
| - | Determination of Safari-1 Neutron Fluxes by MCNPX Modelling of Foil Experiments Dawid De Villiers, Andy Graham, Mohamed Belal 5 - Innovative Methods in research Reactor Physics Document | + | |
| - | Kinetic Parameters Calculation and Measurements During the Opal Commissioning Daniel F. Hergenreder, | + | |
| - | MCNPX 2.6.C vs. MCNPX & ORIGEN-S: State of the Art for Reactor Core Management S. Kalcheva, E. Koonen 5 - Innovative Methods in Research Reactor Physics Document | + | |
| - | Application of Best Estimate Thermalhydraulic Codes for the Safety Analysis of Research Reactors M. Adorni, A. Bousbia Salah, F. D' | + | |
| - | Preparation for the next generation of nuclear power plants Reyes L. A. 0 - Welcoming Session Document | + | |
| - | Keynote Address William Magwood, Former Director, DOE-NE 0 - Welcoming Session Document | + | |
| - | Keynote Address West C. 0 - Welcoming Session Document | + | |
| - | Performance of the New Hihg Flux Neutron Source FRM-II Petry W. 0 - Welcoming Session Document | + | |
| - | The Jules Horowitz Reactor, a new material testing reactor in Europe Iracane D. 0 - Welcoming Session Document | + | |
| - | Progress on the Construction of Australia’s Replacement Research Reactor (OPAL) Miller R. 1 - Technical session 1 Document | + | |
| - | Enhancing Research Reactor Safety – The IAEA’s Approach Brockman 1 - Technical session 1 Document | + | |
| - | First Experience with the Operation of the FRM-II Gerstenberg H. 2 - Operating Reactors and upgrades Document | + | |
| - | Advanced Test Reactor Capabilities and Future Operating Plans Marshall F. 2 - Operating Reactors and upgrades Document | + | |
| - | Status of the High Flux Isotope Reactor and the Reactor Scientific Upgrades Program Selby D. 2 - Operating Reactors and upgrades Document Presentation | + | |
| - | Research Reactor Low Enriched Uranium: Supply, Demand, Capabilities and Quality Hassler M. 3 - Fuel Cycle Developments Document | + | |
| - | Update on the Effort to Develop and Qualify New Low Enrichment Fuels Meyer M. 3 - Fuel Cycle Developments Document | + | |
| - | Scientific Opportunities at OPAL, the Australian Replacement Research Reactor Robinson R. 4 - Research Reactor Utilization Document | + | |
| - | A Preview of Research Projects at the NC State University PULSTAR Reactor Cook A. 4 - Research Reactor Utilization Document | + | |
| - | Irradiation Devices for Materials Studies in the Jules Horowitz Reactor Yvon P. 4 - Research Reactor Utilization Document 1 Document 2 | + | |
| - | MIT Research Reactor as a National User Facility for Advanced Materials and Fuel Research Hu | + | |
| - | An Overview of Current Projects | + | |
| - | Jules Horowitz Reactor Experimental Capabilities Gaillot S. 4 - Research Reactor Utilization Document Presentation | + | |
| - | Operating Licensing Results Doyle P. 5A - Licensing Document | + | |
| - | Licensing Issues Hughes D. 5A - Licensing Document | + | |
| - | The FRM-II Hot and Cold Neutron Sources Müller C. 5B - Secondary Sources Document Presentation | + | |
| - | Installation and Testing of the OPAL (RRR) Cold Neutron Source Thiering R. 5B - Secondary Sources Document | + | |
| - | High Flux Isotope Reactor (HFIR) Cold Source Safety Analysis Cook D. 5B - Secondary Sources Document | + | |
| - | Jules Horowitz Reactor: General Lay Out, Main Design Options Resulting From Safety Options, Technical Performances and Operating Constraints Bravo X. 6A - New Reactor Facilities Document | + | |
| - | The Jules Horowitz Reactor Core and Cooling Circuits Design Pascal C. 6A - New Reactor Facilities Document Presentation | + | |
| - | OPAL Reactor Commissioning and Operations Planning Vittorio D. 6A - New Reactor Facilities Document 1 Presentation | + | |
| - | Planning for Final Operation of the HIFAR Reactor Vittorio D. 6A - New Reactor Facilities Document Presentation | + | |
| - | Kansas State University (KSU) Reactor License Renewal Experience Whaley M. 6A - New Reactor Facilities Document | + | |
| - | Accelerator Driven Subcritical Experiments at The University of Texas O’Kelly S. 6A - New Reactor Facilities Document | + | |
| - | Design of a gas test loop facility for the advanced test reactor Wemple C. 7A - Reactor Utilization Document | + | |
| - | Developing Irradiation Devices for Fuel Experiments in the Jules Horowitz Reactor Parrat D. 7A - Reactor Utilization Document | + | |
| - | The New CABRI Water Loop: Detailed Description of the New Water Loop and of the Specific New Zircaloy in Core Experimental Cell Bourguignon D. 7A - Reactor Utilization Document 1 Document 2 | + | |
| - | Research Reactor in the Event Of an Earthquake: Safety Targets, Technical Approaches and Work Carried Out Plewinski F. 7B - Reactor Safety Document | + | |
| - | Disparities in the Safety Demonstrations for Research Reactors and Need for Harmonization Abou Yehia H. 7B - Reactor Safety Document Presentation | + | |
| - | CABRI Reactor Safety Re-Assessment Massieux S., Couturier 7B - Reactor Safety Document | + | |
| - | Isotope Ratio Method Analysis of the Ford Nuclear Reactor Gesh C. 8A - Decommissioning Document Presentation | + | |
| - | Characterization of a University TRIGA Reactor Taylor K. 8A - Decommissioning Document | + | |
| - | DOE University programs Guttridge J. 8B - DOE Research Reactor Programs Document | + | |
| - | 2005 Status Report for the University Reactor Fuel Assistance Program Vinnola A. 8B - DOE Research Reactor Programs Document | + | |
| - | The process for shipment of test, research and training reactor spent nuclear fuel (SNF) to the INL Robb A. and Wahnschaffe | + | |
| - | SUNRISE - A regional concept for University research reactors Kochendarfer, | + | |
| - | A Computational Model of the High Flux Isotope Reactor: Validation and Application to Low Enriched Uranium Fuels Xoubi N. 9A - Computational Methods Document Presentation | + | |
| - | Determination of Inventories and Power Distributions for the NBSR Hanson A. 9A - Computational Methods Document Presentation | + | |
| - | Core Design for Neutron Flux Maximization in Research Reactors Teruel F. 9A - Computational Methods Document Presentation | + | |
| - | Global threat reduction approach Anne C. 9A - Computational Methods Document | + | |
| - | The IPR-R1 TRIGA Mark I Reactor: Improving the Brazilian Nuclear Technology in 45 Years of Operation Fausto M. 9B - Reactor Utilization Document | + | |
| - | Material and Fuel Testing in the OSIRIS Reactor Durande-Ayme Ph. 9B - Reactor Utilization Document | + | |
| - | Instrumented Fuel Plate for IRIS Irradiation Program in the OSIRIS Reactor Boulcourt P. 9B - Reactor Utilization Document Presentation | + | |
| - | The FRG-1 Cold Neutron Source - Measures for High Neutron Flux and Availability Knop W. 9C - Secondary Sources Document | + | |
| - | Current Status of the HANARO CNS Moderator Cell Design Yu Y.J. 9C - Secondary Sources Document Presentation | + | |
| - | Special Constructional Design Features of Cold and Hot Neutron Sources and Confirmation/ | + | |
| - | Analysis of the Causes and Consequences of Neutron Guide Tube Failures Rowe J.M. 9C - Secondary Sources Document Presentation | + | |
| - | Feasibility of a Liquid Deuterium Cold Source at NIST Williams R. E. 9C - Secondary Sources Document | + | |
| - | The Recent Upgrade to the Penn State TRIGA Reactor Control and Monitoring System Heidrich B. 9D - 50th Anniversary: | + | |
| - | Transient Rod Drop Time - A Synopsis of a Reportable Event Bryan M.E. 9D - 50th Anniversary: | + | |
| - | Neutron Imaging at Penn State: Past, Present and Future Brenizer J. 9E - Reactor Utilization Document | + | |
| - | Facilities, | + | |
| - | Development of Time-Of-Flight and Neutron Depth Profiling at Penn State University Cetiner S. 9E - Reactor Utilization Document | + | |
| - | Inspecting a research reactor' | + | |
| - | Replacement of the Regulating Rod in the Reed Research Reactor Barnett R.C. 9F - Operations and Maintenance Document | + | |
| - | OPAL Licensing Ordonez J.P. 9G - Licensing and Safety Document | + | |
| - | Radiation-Induced Growth in Zircaloy-4 under Research Reactor Operating Conditions Harrison R. 9G - Licensing and Safety Document | + | |
| - | Seismic Strengthening of the ILL High Flux Reactor Building Germane L. 9G - Licensing and Safety Document | + | |
proceedings/2009_igorr12.1703744890.txt.gz · Last modified: 2023/12/28 07:28 by Joerg Pulz