proceedings:2014_igorr16
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| ===== November 2014, Bariloche, Argentina ===== | ===== November 2014, Bariloche, Argentina ===== | ||
| - | ^ Title ^ Author(s) ^ | + | < |
| - | | A Core Pressure Drop Monitoring System: Design and implementation at the RA6 Research Reactor | F. Brollo | | + | ^ Title ^ Author(s) |
| - | | 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 | | + | | {{ : |
| + | | {{ : | ||
| + | </ | ||
proceedings/2014_igorr16.1703748496.txt.gz · Last modified: 2023/12/28 08:28 by Joerg Pulz