proceedings:2014_igorr16
This is an old revision of the document!
| Title | Author(s) |
|---|---|
| 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/Unloading Irradiation Targets in a Research Reactor | Hyeonil Kim |
| 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, Safety and Aging Management of the High Flux Isotope Reactor at Oak Ridge National Laboratory | R. A. Crone |
| Wide Range Amplifier for Neutron Flux Measurement | L. Giuliodori |
proceedings/2014_igorr16.1703745981.txt.gz · Last modified: 2023/12/28 07:46 by A User Not Logged in