proceedings:2009_igorr12
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| ===== October 2009 - Beijing, China ===== | ===== October 2009 - Beijing, China ===== | ||
| - | ^ Title ^ Author(s) ^ Session ^ Misc ^ | + | < |
| - | | The Jules Horowitz Reactor: A new European MTR open to International collaboration | G.BIGNAN | Session 1: New Reactor and General Research Reactor | | | + | ^ Title |
| - | | Research Reactors from Argentine Origin | J.P.ORDONEZ | Session 1: New Reactor and General Research Reactor | | | + | | {{ :proceedings:2009_igorr12:igorr_2009_presentation.pdf |Opening Lecture « Nuclear Renaissance and the key role of Research Reactors »}} | J.GUIDEZ |
| - | | Future of French Design and Construction Code for Research Reactors | C.PASCAL; B.DRUBAY | Session 1: New Reactor and General Research Reactor | Full paper| | + | | {{ : |
| - | | Implementation of Molybdenum Production in Polish Research Reactor MARIA | A.GOLAB | Session 10: Research Reactor Utilization II | | | + | | {{ : |
| - | | Thermal Assessment of the CALIPSO Irradiation Device for the Jules Horowitz Reactor | D.MOULIN | Session 10: Research Reactor Utilization II | Full paper| | + | | {{ : |
| - | | The MADISON Experimental Hosting System in the Future Jules Horowitz Reactor | P.ROUX | Session 10: Research Reactor Utilization II | Full paper| | + | | {{ : |
| - | | Reactivity Challenges of the EVITA Irradiation Program at BR2 | E.KOONEN | Session 10: Research Reactor Utilization II | | | + | | {{ : |
| - | | Conducting a State Systems of Accounting for and Control of Nuclear Materials Training Program | L.P. FOYTO | Session 10: Research Reactor Utilization II | | | + | | {{ : |
| - | | Refurbishment and Upgrade of ILL Reactor and Instrument Suite | H.J GUYON | Session 3: Research Reactor Modifications | | | + | | {{ : |
| - | | Neutron Commissioning in the CABRI Water Loop Facility | G.RITTER | Session 3: Research Reactor Modifications | Full paper| | + | | {{ : |
| - | | Design and Construction of a Zircaloy Pressure Vessel for the Research Reactor CABRI | D.BOURGUIGNON | Session 3: Research Reactor Modifications | Full paper| | + | | {{ : |
| - | | PROTEUS Upgrade – Modernization and Refurbishment of the PROTEUS Facility | G.PERRET | Session 3: Research Reactor Modifications | | | + | | {{ : |
| - | | NRU Reactor Vessel Repair | G.B WILKIN | Session 3: Research Reactor Modifications | | | + | | {{ : |
| - | | 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 | | | + | | {{ : |
| - | | 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 | Full paper| | + | | {{ : |
| - | | LIFE @ PROTEUS Experimental Program | G.PERRET | Session 4: Operating Reactors and Critical Facilities | | | + | | {{ : |
| - | | Jules Horowitz I&C Overview | L.RODRIGUEZ | Session 5: Instrumentation and Control | Full paper| | + | | {{ : |
| - | | Performance Indicators for Research Reactors | G.STORR | Session 6: Operations and Maintenance | | | + | | {{ : |
| - | | Configuration Control and Implementation of Safety Principles on the Research Side of the HFIR Site Operations | D.SELBY | Session 6: Operations and Maintenance | | | + | | {{ : |
| - | | OPAL Reflector Vessel – Repairs Options to Mitigate Light Water Leaks | R.THIERING | Session 6: Operations and Maintenance | | | + | | {{ : |
| - | | OPAL Engineering Early Modifications Relating to DBA Loss of Offsite Power (LOOP) | P.METCALF | Session 7: Research Reactor Safety | | | + | | {{ : |
| - | | Reactivity Insertions for the Borax Accident in ORPHEE Reactor | Y.CHEGRANI | Session 7: Research Reactor Safety | | | + | | {{ : |
| - | | Safety and Reliability Improvements in OSIRIS | G.BIGNAN | Session 7: Research Reactor Safety | | | + | | {{ : |
| - | | Overcoming Challenges in the ZED-2 Reactor Safety Analysis | G.B WILKIN | Session 7: Research Reactor Safety | | | + | | {{ : |
| - | | Status of Cold Neutron Research Facility Installation in HANARO | I.C LIM | Session 8: Secondary Sources | | | + | | {{ : |
| - | | Maintenance, | + | | {{ : |
| - | | The Ultra-Cold Neutron Laboratory at the FRM-II | A.FREI | Session 8: Secondary Sources | | | + | | {{ : |
| - | | he JHR MOLY System: Towards a Concept Proposal According a Large Molydenum Production Capabilities | S.GAILLOT | Session 9: Research Reactor Utilization I | 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 | Full paper| | + | | {{ : |
| - | | The IAEA Activities in Support of Research Reactor Utilization and Applications | D.RIDIKAS | Special Plenary Session | | | + | | {{ : |
| - | | Towards the Renewal of the European Research Area of Experimental Reactors: The MYRRHA Project | P.BAETAN | Welcoming session | | | + | | {{ : |
| - | | Opening Lecture « Nuclear Renaissance and the key role of Research Reactors » | J.GUIDEZ | 0 - General Session | | | + | | {{ : |
| - | | The new Research Reactors of CIAE: CARR and CEFR | PR. Y.LUZHENG; DR. S. FENG | 0 - General Session | | | + | | {{ : |
| - | | 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 | 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 | Sustaining Material Testing Capacity in France:From OSIRIS to JHR| | + | | {{ : |
| - | | Australia’s new Research Reactor-OPAL | G.J. Storr | 0 - General Session | 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 | Refurbishment Status and Future Program of Japan Material Testing Reactor JMTR| | + | | {{ : |
| - | | Current Status of HANARO and Future Plan | In-Cheol LIM, Young-Ki KIM, Ki-Honh LEE, Jae-Joo Ha | 0 - General Session | Current Status of HANARO and Future Plan| | + | | {{ : |
| - | | The High Flux Isotope Reactor: Past, Present and Future | Kelly Beierschmitt | 0 - General Session | 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 | 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 | 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 | | | + | | {{ : |
| - | | Experimental Research Reactor LVR15 : Present status and Programs | J. Kysela, J.Prahl | 0 - General Session | Experimental Research Reactor LVR15 : Present status and Programs| | + | | {{ : |
| - | | IAEA’s Subprogramme on Research Reactors | P. Adelfang | 0 - General Session | | | + | | {{ : |
| - | | Multiple purpose research reactors for the 21st century | W. Petry | 0 - General Session | | | + | | {{ : |
| - | | Present Status and Future Plans of the Halden Reactor | M. A. McGrath | 0 - General Session | | | + | | {{ : |
| - | | Research Reactors at the French Atomic Energy. Commission: Past, present and future | P. Raymond | 1 - New Project and General Strategy | Research Reactors| | + | </datatables> |
| - | | The current status of neutrons scattering facilities at CARR | Yuntao Liu | 1 - New Project and General Strategy | | | + | |
| - | | 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 | Irradiation effects on 6061-T6 Aluminium alloy used for JHR Internal Structures| | + | |
| - | | The progress of CARR’s neutron image facilities | Hongli Wang | 1 - New Project and General Strategy | | | + | |
| - | | 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 | Presentation| | + | |
| - | | Fundamental research on Molten Salt Reactors | Dalin Zhang | 1 - New Project and General Strategy | 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 | Presentation| | + | |
| - | | Underwater NDE Systems in the JHR : Towards integration issues | G. Le Guillou, B. Berthet, S. Gaillot | 1 - New Project and General Strategy | 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 | | | + | |
| - | | 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, P.Alexandre, | + | |
| - | | 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 | Presentation| | + | |
| - | | Studies of Past Operations at the High Flux Isotope Reactor | R.T. Primm, D. Chandler | 2 - Enrichment Conversion | Presentation| | + | |
| - | | OPAL Commissioning and Early Operation : A Shift Manager’s perspective | CK. Teoh | 3 - Research Reactor Operation and Improvement | Presentation| | + | |
| - | | The Safety Review and Update of the Safety Analysis Report for the OPAL Reactor | M.W. Summerfield | 3 - Research Reactor Operation and Improvement | Presentation| | + | |
| - | | OPAL Cold Neutron Source Heat Load Measurement | Weijian LU | 3 - Research Reactor Operation and Improvement | 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 | Presentation| | + | |
| - | | Advanced Test Reactor and Experiment Research Program | F.M. Marshall, S. Blaine Grover | 3 - Research Reactor Operation and Improvement | Presentation| | + | |
| - | | Current Status of the Spent Fuel Management in HANARO | Mun.Lee, C.S Lee, K.W Lim, H.W Lim, K.H Ahn, I.C Lim | 3 - Research Reactor Operation and Improvement | Presentation| | + | |
| - | | 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 | Presentation| | + | |
| - | | MERCI-MOSAIC: | + | |
| - | | Present Status of Operation and Maintenance of JRR-3 | T.Ichimura, M.Suwa, M.Fukushima, | + | |
| - | | Some essential features of the TAPIRO Fast-Neutron Source Reactor located at ENEA-CRE Casaccia | R. Rosa, M.Carta, O.Fiorani, A.Santagata | 3 - Research Reactor Operation and Improvement | Presentation| | + | |
| - | | How can the availability of safe and secure Research reactors be assured in future? | C.Hansell | 4 - Generalities | Presentation| | + | |
| - | | Questioning the Self-Protection of Nuclear Materials At Research Reactors around the world | F.Dalnoki Veress | 4 - Generalities | | | + | |
| - | | 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 | Presentation| | + | |
| - | | Neutronic characterization and safety assessment Of CABRI core | O.Gueton, G.Ritter, F.Jeury, C.Hee, B.Duc, C.Doderlein | 5 - Research Reactors Refurbishment | Presentation| | + | |
| - | | Building a new safety case for the nuclear core of CABRI | G. Ritter (presented by J.Estrade), F. Jeury | 5 - Research Reactors Refurbishment | 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 | Presentation| | + | |
| - | | Validation and qualification of the ANUBIS scheme, Used for safety assessment and operation management Of the OSIRIS reactor | O.Gueton, P.Sireta, C.Doderlein, | + | |
| - | | Fuel Rod Instrumentation Techniques implemented In CEA hot Laboratory: Improvement and Experimental feed-back | F. Berdoula, K.Silberstein, | + | |
| - | | A Core Pressure Drop Monitoring System: Design and implementation at the RA6 Research Reactor | F. Brollo | | | | + | |
| - | | Adaptation of ANUBIS scheme to SAFARI-1 core characterisation | L. Moloko | | | | + | |
| - | | ADVANCE IN THE RA-10 REACTOR PROJECT | H. Blaumann | | | | + | |
| - | | Ageing Management Programme for Research Reactors in Argentina | G. Vega | | | | + | |
| - | | Ageing Management, Obsolescence and Refurbishment of GHARR-1 Structures, Systems and Components (SSCs) | E.O. Amponsah-Abu | | | | + | |
| - | | 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 | | | | + | |
| - | | Analysis of a Loss of Offsite Power Event for the RA-10 Reactor | S. Papadakis | | | | + | |
| - | | Analysis of an Inadvertent Control Plate Withdrawal Event in the RA-10 Reactor | R. Maturana | | | | + | |
| - | | Analysis on LCO for On-Power Loading/ | + | |
| - | | CFD Models of the RA-10 RI Facilities: A Useful Tool for Design Support | M. Gramajo | | | | + | |
| - | | Characterization of UO2-Gd2O3 nuclear fuel obtained by co-precipitation by Transmission Electron Microscopy | I. Gana | | | | + | |
| - | | CNEA DEVELOPMENTS IN U-Mo-Zry-4 MINIPLATES AND PLATES CO-ROLLING CONTROL | B. Picchetti | | | | + | |
| - | | COCONEUT: An innovative deterministic neutronic calculation tool for research reactors | J.-G. Lacombe | | | | + | |
| - | | Conceptual Design of a Compact Nuclear Reactor Core | R.Vignolo | | | | + | |
| - | | Conceptual Design of a Research Reactor with Monolithic UMo Fuels | J.I. Beliera | | | | + | |
| - | | Conceptual Design of the Core of an ADS (Accelerator Driven System) | M. Tacca | | | | + | |
| - | | Contributions of CFD to the analysis of the second shutdown system of the RA-10 research reactor | L. M. Rechiman | | | | + | |
| - | | Correction factors to apply to fission rates measured by miniature fission chambers in various neutron spectra | B. Geslot | | | | + | |
| - | | Creativity in Cold Neutron Sources Design | L. Manifacier | | | | + | |
| - | | CURRENT STATUS OF JRR-3 | Y. Kashima | | | | + | |
| - | | Current Status of the KJRR Project and its Design Features | C.Park | | | | + | |
| - | | Cyber Security Study for Research Reactors | J. Shin | | | | + | |
| - | | Density determination of pyrotechnical devices using neutron imaging techniques on the RA-6 reactor | N. Chiaraviglio | | | | + | |
| - | | DEPLETION ANALYSIS OF THE OPAL REACTOR WITH VESTA | P.Young | | | | + | |
| - | | Description and Applications of the Neutron Imaging Facility at RA-6 | J. Marin | | | | + | |
| - | | Design and first operation of the DIAMINO (U241AmO2) experiment in OSIRIS MTR for Am-recycling program | S. BENDOTTI, C. NEYROUD, S. BEJAOUI, T. LAMBERT | | | | + | |
| - | | Design of a calibration beam for detector characterization | J. M. Longhino | | | | + | |
| - | | Development of Emergency Operating Guidelines for a Research Reactor | Hyeonil Kim | | | | + | |
| - | | Development of Equipment for Simulating Coolant Flow in a Test Rig | J. T. Hong | | | | + | |
| - | | Development of Laser Welding Technology for Fabricating Nuclear Fuel Test Rig | C.Y. Joung | | | | + | |
| - | | Development of Safety Management Portal System for HANARO Research Reactor | Hoan Sung Jung | | | | + | |
| - | | Deviation from ASME III Code rules for the design of Research Reactors | M. Wesley | | | | + | |
| - | | 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 | | | | + | |
| - | | Dog-Bone Studies In U-Mo-Zry-4 Miniplates Fabrication Process | M. Lopez | | | | + | |
| - | | Education and Training at Low Power Research Reactor VR-1 for National and International Students and Trainees | Lubomir Sklenka - Czech Republic | | | | + | |
| - | | ENEA Thermal and Fast Research Reactors utilization for R&D activities at Casaccia Center | M. Sepielli | | | | + | |
| - | | Expansion of the Cold Neutron Facilities and Reactor Upgrades at the NIST Center for Neutron Research | R. E. Williams | | | | + | |
| - | | Experimental Investigation of Operational Parameters in the CDTN TRIGA Reactor | A.Z Mesquita | | | | + | |
| - | | Experimental Study on Downward Two-Phase Flow in Vertical Narrow Rectangular Channel | J.H. Jeong | | | | + | |
| - | | FPGA Based Reactor Protection System Architecture | C.A. Verrastro | | | | + | |
| - | | FRM II: Results and experience of the major maintenance shutdown after ten years of operation | A. Pichlmaier | | | | + | |
| - | | Heat Deposition in Out-Core Devices of Research Reactors after Actuation of a Shutdown System Based on Reflector Tank Draining | H. Meier | | | | + | |
| - | | High Order Finite Elements for Reactor Calculation. Examples and Comparison with Experimental Results | Carlos R. Grant | | | | + | |
| - | | Implementation and Utilization of Positron Annihilation Spectrometry Methods at the PULSTAR Reactor | A. I. Hawari | | | | + | |
| - | | Implementation of a Periodic Safety Review of HANARO Research Reactor | Minjin Kim | | | | + | |
| - | | Implementation of the Neutron Noise Technique for Measurement of Reactivity in Subcritical of the Low Power Research Reactor RA-4 | J. Orso | | | | + | |
| - | | IMPROVING IMMUNITY OF THE OPAL REACTOR TO ELECTRICAL POWER DISTURBANCES | B. GITTOES | | | | + | |
| - | | Instrumentation & Control Systems for the Brazilian Multipurpose Reactor - RMB | P. Carvalho | | | | + | |
| - | | Integral (n,y) Cross-sections Measurement of Standard Light Water Reactors Materials | A. Gruel | | | | + | |
| - | | Investigation of Mixed Enrichment Core Loadings for the PULSTAR Reactor | A. I. Hawari | | | | + | |
| - | | IRRADIATION CAPSULE DESIGN TO SUPPORT DOE RESUMPTION OF US 60Co ISOTOPE PRODUCTION | R. Howard | | | | + | |
| - | | Irradiation Facilities Performance at RA-10 | F. Sanchez | | | | + | |
| - | | Irradiation Loop Facility in RA-10 Reactor | L. Vazquez | | | | + | |
| - | | Irradiation Requirements for Radioisotope Production | D. Hergenreder | | | | + | |
| - | | JULES HOROWITZ REACTOR OPERATION IN MOCK-UP MODES | J. Estrade | | | | + | |
| - | | Jules Horowitz Reactor: organization for the preparation of the commissioning phase and normal operation | J. Estrade | | | | + | |
| - | | Kinetic Parameters Estimation in the RA-0 Research Reactor | P. Bellino | | | | + | |
| - | | LEVEL 1 PROBABILISTIC SAFETY ASSESSMENT FOR LICENSING OF RA-10 REACTOR | M. Grinberg | | | | + | |
| - | | LEVEL 2 AND 3 PROBABILISTIC SAFETY ASSESSMENT FOR LICENSING OF RA-10 REACTOR | C. Mulleady | | | | + | |
| - | | LORELEI: A future Test Device for LOCA Experiments in the JHR | L. Ferry | | | | + | |
| - | | Materials Surveillance Programme for the RA10 Research Reactor | R. Versaci | | | | + | |
| - | | Measurement of Fission Products and Chemical Species released by Experimental Samples irradiated in the Jules Horowitz Reactor | D. Parrat | | | | + | |
| - | | Measurement of the Xenon-135 Reactivity Evolution after a Shutdown in the RA-3 Research and Production Reactor | P. Bellino | | | | + | |
| - | | Mechanicals description of RA-10 Reactor and Service Pool and main Core Components | A. Coleff | | | | + | |
| - | | More than Forty Years of Neutronics Experiments in Critical Facilities of Cadarache Center: From EOLE and MINERVE to the Future ZEPHYR Reactor | S. Cathalau | | | | + | |
| - | | Neutron Absorbing Glass Microspheres as Second Shutdown System | I. Gana | | | | + | |
| - | | Neutron and Gamma Shielding Design of the Neutron Guide Primary Shutter in a Research Reactor | A. Maître | | | | + | |
| - | | Neutron Cold Source Optimization for RA-10 reactor | A. Marquez | | | | + | |
| - | | Neutron Flux and Reactor Kinetic parameters Calculations in the RA0 Reactor | L. Romero | | | | + | |
| - | | Neutronic Analysis of the Jamaican SLOWPOKE-2 Research Reactor for the Conversion from HEU to LEU Fuel | H. Dennis | | | | + | |
| - | | Neutronic Calculation Methodology for Research Reactors | E. Villarino | | | | + | |
| - | | Neutronic Design of the RA10 Research Reactor´s Core | J.M.Tunon | | | | + | |
| - | | Neutronic Design of the RMB Research Reactor | J.M.Tunon | | | | + | |
| - | | Neutronic Simulation of IPR-R1 TRIGA First Configuration using Serpent and MCNP Codes | S. P. de Meireles | | | | + | |
| - | | New Core with Low-Enriched Uranium Fuel at the Kazakhstan Critical Facility | A. Shaimerdenov | | | | + | |
| - | | Nuclear Education & Training activity experience at the University of Pavia | A. Salvini | | | | + | |
| - | | Nuclear Instrumentation System of RA-10 | G. Quesada | | | | + | |
| - | | Numerical Investigation of Cooling in the Pool of the Brazilian Multipurpose Reactor (RMB) | A.Z Mesquita | | | | + | |
| - | | OPAL Reactor Full 3-D Calculations using the MonteCarlo Code Serpent 2 | Diego Ferraro | | | | + | |
| - | | Operation and Utilisation of Low Power Research Reactor Critical Facility for Advanced Heavy Water Reactor (AHWR) | S. K. De | | | | + | |
| - | | OPERATION, MAINTENANCE EXPERIENCE AND FUTURE CHALLENGES OF TRIGA RESEARCH REACTOR OF BANGLADESH | M. A. Salam | | | | + | |
| - | | Optimisation Approach to Asses Seismic Reinforcements of a Low Power Research Reactor | M. Auzas | | | | + | |
| - | | PARCS Few-group Homogenized Parameters Generation using Serpent Monte Carlo code at the CROCUS Reactor | A. Rais | | | | + | |
| - | | Preliminary Studies on A New Research Reactor and Cold Neutron Source at NIST | Zeyun Wu | | | | + | |
| - | | Preparation and Submission of a Manuscript for the Proceedings of the Technical Meeting | A. Malaquias | | | | + | |
| - | | Production Facilities for Reactor Produced Radioisotopes | J. Merino | | | | + | |
| - | | RA10 - Utilization-driven Layout | N. De Lorenzo | | | | + | |
| - | | RA-10 Design Management: Strategic Objectives and Specific Actions | F. Brollo | | | | + | |
| - | | RA-10 Project Safety Assessment and Licensing Process | P. Ramirez | | | | + | |
| - | | Relevant Characteristics of the RA-10 I&C Systems | P. Cantero | | | | + | |
| - | | Relicensing of the SM1 Sub-critical assembly of the Pavia University | L. Strada | | | | + | |
| - | | Renovation, improvement and experimental validation of the Helium-3 transient rods system for the reactivity injection in the CABRI reactor | B. Duc | | | | + | |
| - | | Replacement of the Oregon State University TRIGA® Reactor Annular Reflector | S. Todd Keller | | | | + | |
| - | | Research Institute of Atomic Reactors | D. Fomin | | | | + | |
| - | | Research Reactor Spent Fuel Management in Argentina | L. Mottillo | | | | + | |
| - | | Review of low-power research reactor developed for education and training | In-Cheol Lim - Korea | | | | + | |
| - | | RMB: THE NEW BRAZILIAN MULTIPURPOSE RESEARCH REACTOR | J.A. Perrotta | | | | + | |
| - | | Simplified Method For Thermal-Hydraulic Design And Evaluation Of Research Reactor Core, Coupled With Neutronic Montecarlo Calculation | M.A.N Giménez | | | | + | |
| - | | SIREx: Instrumentation System for Research Reactors | F.D. Rossi Mescolatti | | | | + | |
| - | | Start-up of a New Storage Facility for Spent Fuel from Research Reactors at CNEA | O. Novara | | | | + | |
| - | | Status of uranium targets irradiation in MARIA reactor for molybdenum production | G. Krzysztoszek | | | | + | |
| - | | The Enhancement of VR-1 Reactor Utilization for Practical Education Using Portable Neutron Generator | J. Rataj | | | | + | |
| - | | The IPEN/MB-01 zero power reactor and the LABGENE reactor experimental programme | P. Piovezan | | | | + | |
| - | | 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 | | | | + | |
| - | | The RMB Research Reactor Project | C. Mazufri | | | | + | |
| - | | Thermal-Hydraulic Aspects for the Upgrade of a Research Reactor | C. Pavon | | | | + | |
| - | | Thermal-hydraulic aspects of RMB design | J. Lupiano Contreras | | | | + | |
| - | | TRACE Code Application to Low Operating Pressure Research Reactor Safety Analysis | A. Rais | | | | + | |
| - | | Trace element Content of Zingiber Officinalis and Salvia Officinalis plants from Algeria | Z.Lamari | | | | + | |
| - | | Transmutation Experimental Facility for Research and Development of Accelerator-Driven System in JAEA | K. Tsujimoto | | | | + | |
| - | | Use of Pulse-Mode Neutron Flux-Change-Rate as a Trip Condition in a Nuclear Reactor | F.N. Ferrucci | | | | + | |
| - | | Use Virtual Environments for Training in Nuclear Facilities | P. Carvalho | | | | + | |
| - | | Utilization of the Dalat Research Reactor After Its Core Conversion | N. Nhi Dien | | | | + | |
| - | | Utilization of the High Flux Isotope Reactor at Oak Ridge National Laboratory | D. L. Selby | | | | + | |
| - | | Utilization, | + | |
| - | | Wide Range Amplifier for Neutron Flux Measurement | L. Giuliodori | | | | + | |
| - | | Refurbishment and Activities at Tajoura Reactor | Feisal Abutweirat, Mohammed Busitta | 1 - International Topics and Overview on New Projects and Fuel Developments | | | + | |
| - | | 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 | | | + | |
| - | | 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 | | | + | |
| - | | Irradiation Facilities at the Advanced Test Reactor | S. Blaine Grover | 1 - International Topics and Overview on New Projects and Fuel Developments | | | + | |
| - | | The Renaissance of Sodium Fast Reactors Status and Contribution of Phenix | J. Guidez | 1 - International Topics and Overview on New Projects and Fuel Developments | | | + | |
| - | | 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 | | | + | |
| - | | 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 | | | + | |
| - | | The Opal Reactor | R. Miller, T. Irwin | 1 - International Topics and Overview on New Projects and Fuel Developments | | | + | |
| - | | 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 | | | + | |
| - | | 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 | | | + | |
| - | | 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 | | | + | |
| - | | Development of High Temperature Capsule for RIA-Simulating Experiment with High Burnup Fuel | Toshiyuki Suzuki, Miki Umeda | 2 - New Projects and Upgrades | | | + | |
| - | | New Silicon Irradiation Rig Design for Opal Reactor | Peter Amos | 4 - Optimisation and Research Reactor Utilisation | | | + | |
| - | | Residual Heat Estimation by Image Processing Using Cherenkov Radiation in TRR | M. Arkani, M. Gharib | 4 - Optimisation and Research Reactor Utilisation | | | + | |
| - | | Materials Surveillance Program for the Opal Research Reactor | Bob Harrison | 4 - Optimisation and Research Reactor Utilisation | | | + | |
| - | | 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 | | | + | |
| - | | 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 | | | + | |
| - | | Status of the High Flux Isotope Reactor Cold Source Project | Ken Morgan, Douglas Selby | 4 - Optimisation and Research Reactor Utilisation | | | + | |
| - | | Overview of the IAEA Activities on Safety of Research Reactors | A.M. Shokr | 4 - Optimisation and Research Reactor Utilisation | | | + | |
| - | | 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 | | | + | |
| - | | Determining MTR RIA Limits Using Experimental Data | Simon E. Day | 5 - Innovative Methods in research Reactor Physics | | | + | |
| - | | 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 | | | + | |
| - | | 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 | | | + | |
| - | | 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 | | | + | |
| - | | Radiation Protection Design of the FRM II | Wolfgang Dittrich, Helmut Zeising | 6 - Safety, Operation and Research Reactor Conversion | | | + | |
| - | | 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 | | | + | |
| - | | 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 | | | + | |
| - | | 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 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 | | | + | |
| - | | Safari-1 : Adjusting Priorities During the LEU Conversion Program | C. Piani | 6 - Safety, Operation and Research Reactor Conversion | | | + | |
| - | | 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 | | | + | |
| - | | Conversion of Research and Test Reactors : Status and Current Plans | Parrish Staples, Nicholas Butler, Jordi Roglans | 6 - Safety, Operation and Research Reactor Conversion | | | + | |
| - | | U.S. Domestic Reactor Conversion Programs | Dana Meyer, Eric Woolstenhulme | 6 - Safety, Operation and Research Reactor Conversion | | | + | |
| - | | 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 | | | + | |
| - | | 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 | | | + | |
| - | | 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 | | | + | |
| - | | 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 | | | + | |
| - | | Keynote Address | William Magwood, Former Director, DOE-NE | 0 - Welcoming Session | | | + | |
| - | | Keynote Address | West C. | 0 - Welcoming Session | | | + | |
| - | | Performance of the New Hihg Flux Neutron Source FRM-II | Petry W. | 0 - Welcoming Session | | | + | |
| - | | The Jules Horowitz Reactor, a new material testing reactor in Europe | Iracane D. | 0 - Welcoming Session | | | + | |
| - | | Progress on the Construction of Australia’s Replacement Research Reactor (OPAL) | Miller R. | 1 - Technical session 1 | | | + | |
| - | | Enhancing Research Reactor Safety – The IAEA’s Approach | Brockman | 1 - Technical session 1 | | | + | |
| - | | First Experience with the Operation of the FRM-II | Gerstenberg H. | 2 - Operating Reactors and upgrades | | | + | |
| - | | Advanced Test Reactor Capabilities and Future Operating Plans | Marshall F. | 2 - Operating Reactors and upgrades | | | + | |
| - | | Status of the High Flux Isotope Reactor and the Reactor Scientific Upgrades Program | Selby D. | 2 - Operating Reactors and upgrades | + | |
| - | | Research Reactor Low Enriched Uranium: Supply, Demand, Capabilities and Quality | Hassler M. | 3 - Fuel Cycle Developments | | | + | |
| - | | Update on the Effort to Develop and Qualify New Low Enrichment Fuels | Meyer M. | 3 - Fuel Cycle Developments | | | + | |
| - | | Scientific Opportunities at OPAL, the Australian Replacement Research Reactor | Robinson R. | 4 - Research Reactor Utilization | | | + | |
| - | | A Preview of Research Projects at the NC State University PULSTAR Reactor | Cook A. | 4 - Research Reactor Utilization | | | + | |
| - | | Irradiation Devices for Materials Studies in the Jules Horowitz Reactor | Yvon P. | 4 - Research Reactor Utilization | Document 2| | + | |
| - | | MIT Research Reactor as a National User Facility for Advanced Materials and Fuel Research | Hu L.W. | 4 - Research Reactor Utilization | | | + | |
| - | | An Overview of Current Projects | + | |
| - | | Jules Horowitz Reactor Experimental Capabilities | Gaillot S. | 4 - Research Reactor Utilization | Presentation| | + | |
| - | | Operating Licensing Results | Doyle P. | 5A - Licensing | | | + | |
| - | | Licensing Issues | Hughes D. | 5A - Licensing | | | + | |
| - | | The FRM-II Hot and Cold Neutron Sources | Müller C. | 5B - Secondary Sources | Presentation| | + | |
| - | | Installation and Testing of the OPAL (RRR) Cold Neutron Source | Thiering R. | 5B - Secondary Sources | | | + | |
| - | | High Flux Isotope Reactor (HFIR) Cold Source Safety Analysis | Cook D. | 5B - Secondary Sources | | | + | |
| - | | Jules Horowitz Reactor: General Lay Out, Main Design Options Resulting From Safety Options, Technical Performances and Operating Constraints | Bravo X. | 6A - New Reactor Facilities | | | + | |
| - | | The Jules Horowitz Reactor Core and Cooling Circuits Design | Pascal C. | 6A - New Reactor Facilities | Presentation| | + | |
| - | | OPAL Reactor Commissioning and Operations Planning | Vittorio D. | 6A - New Reactor Facilities | Presentation| | + | |
| - | | Planning for Final Operation of the HIFAR Reactor | Vittorio D. | 6A - New Reactor Facilities | Presentation| | + | |
| - | | Kansas State University (KSU) Reactor License Renewal Experience | Whaley M. | 6A - New Reactor Facilities | | | + | |
| - | | Accelerator Driven Subcritical Experiments at The University of Texas | O’Kelly S. | 6A - New Reactor Facilities | | | + | |
| - | | Design of a gas test loop facility for the advanced test reactor | Wemple C. | 7A - Reactor Utilization | | | + | |
| - | | Developing Irradiation Devices for Fuel Experiments in the Jules Horowitz Reactor | Parrat D. | 7A - Reactor Utilization | | | + | |
| - | | 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 2| | + | |
| - | | Research Reactor in the Event Of an Earthquake: Safety Targets, Technical Approaches and Work Carried Out | Plewinski F. | 7B - Reactor Safety | | | + | |
| - | | Disparities in the Safety Demonstrations for Research Reactors and Need for Harmonization | Abou Yehia H. | 7B - Reactor Safety | Presentation| | + | |
| - | | CABRI Reactor Safety Re-Assessment | Massieux S., Couturier | 7B - Reactor Safety | | | + | |
| - | | Isotope Ratio Method Analysis of the Ford Nuclear Reactor | Gesh C. | 8A - Decommissioning | Presentation| | + | |
| - | | Characterization of a University TRIGA Reactor | Taylor K. | 8A - Decommissioning | | | + | |
| - | | DOE University programs | Guttridge J. | 8B - DOE Research Reactor Programs | | | + | |
| - | | 2005 Status Report for the University Reactor Fuel Assistance Program | Vinnola A. | 8B - DOE Research Reactor Programs | | | + | |
| - | | 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 | Presentation| | + | |
| - | | Determination of Inventories and Power Distributions for the NBSR | Hanson A. | 9A - Computational Methods | Presentation| | + | |
| - | | Core Design for Neutron Flux Maximization in Research Reactors | Teruel F. | 9A - Computational Methods | Presentation| | + | |
| - | | Global threat reduction approach | Anne C. | 9A - Computational Methods | | | + | |
| - | | The IPR-R1 TRIGA Mark I Reactor: Improving the Brazilian Nuclear Technology in 45 Years of Operation | Fausto M. | 9B - Reactor Utilization | | | + | |
| - | | Material and Fuel Testing in the OSIRIS Reactor | Durande-Ayme Ph. | 9B - Reactor Utilization | | | + | |
| - | | Instrumented Fuel Plate for IRIS Irradiation Program in the OSIRIS Reactor | Boulcourt P. | 9B - Reactor Utilization | Presentation| | + | |
| - | | The FRG-1 Cold Neutron Source - Measures for High Neutron Flux and Availability | Knop W. | 9C - Secondary Sources | | | + | |
| - | | Current Status of the HANARO CNS Moderator Cell Design | Yu Y.J. | 9C - Secondary Sources | 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 | Presentation| | + | |
| - | | Feasibility of a Liquid Deuterium Cold Source at NIST | Williams R. E. | 9C - Secondary Sources | | | + | |
| - | | 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 | | | + | |
| - | | Facilities, Uses and Capabilities of NAA at the Radiation and Engineering Center at Penn State | Hauck D. | 9E - Reactor Utilization | | | + | |
| - | | Development of Time-Of-Flight and Neutron Depth Profiling at Penn State University | Cetiner S. | 9E - Reactor Utilization | | | + | |
| - | | Inspecting a research reactor' | + | |
| - | | Replacement of the Regulating Rod in the Reed Research Reactor | Barnett R.C. | 9F - Operations and Maintenance | | | + | |
| - | | OPAL Licensing | Ordonez J.P. | 9G - Licensing and Safety | | | + | |
| - | | Radiation-Induced Growth in Zircaloy-4 under Research Reactor Operating Conditions | Harrison R. | 9G - Licensing and Safety | | | + | |
| - | | Seismic Strengthening of the ILL High Flux Reactor Building | Germane L. | 9G - Licensing and Safety | | | + | |
proceedings/2009_igorr12.1703748410.txt.gz · Last modified: 2023/12/28 08:26 by Joerg Pulz