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proceedings:2014_igorr16 [2023/12/28 07:45] – created Joerg Pulzproceedings:2014_igorr16 [2023/12/29 07:38] (current) – datatables Joerg Pulz
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-^ Title ^ Author(s) ^ +===== November 2014, Bariloche, Argentina ===== 
- 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  +<datatables dom="lrftip" ordering="false"> 
- ADVANCE IN THE RA-10 REACTOR PROJECT H. Blaumann Document  +^ Title                                                                                                                                                                                                                                          ^ Author(s)                                        
- Ageing Management Programme for Research Reactors in Argentina G. Vega Document  +| {{ :proceedings:2014_igorr16:brollo-f.pdf |A Core Pressure Drop Monitoring System: Design and implementation at the RA6 Research Reactor}}                                                                                                     F. Brollo                                        | 
- Ageing Management, Obsolescence and Refurbishment of GHARR-1 Structures, Systems and Components (SSCs) E.O. Amponsah-Abu Document  +| {{ :proceedings:2014_igorr16:lemoloko_iggorr2014_paper_final.pdf |Adaptation of ANUBIS scheme to SAFARI-1 core characterisation}}                                                                                                              | L. Moloko                                        | 
- 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  +| {{ :proceedings:2014_igorr16:advance_in_the_ra-herman-blaumann.doc |ADVANCE IN THE RA-10 REACTOR PROJECT}}                                                                                                                                     H. Blaumann                                      | 
- Analysis of a Loss of Offsite Power Event for the RA-10 Reactor S. Papadakis Document  +| {{ :proceedings:2014_igorr16:gustavovega.doc |Ageing Management Programme for Research Reactors in Argentina}}                                                                                                                                 G. Vega                                          | 
- Analysis of an Inadvertent Control Plate Withdrawal Event in the RA-10 Reactor R. Maturana Document  +| {{ :proceedings:2014_igorr16:edwardabu.docx |Ageing Management, Obsolescence and Refurbishment of GHARR-1 Structures, Systems and Components (SSCs)}}                                                                                          | E.O. Amponsah-Abu                                | 
- Analysis on LCO for On-Power Loading/Unloading Irradiation Targets in a Research Reactor Hyeonil Kim Document  +| {{ :proceedings:2014_igorr16:robertohilal.pdf |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                                         | 
- CFD Models of the RA-10 RI Facilities: A Useful Tool for Design Support M. Gramajo Document  +| {{ :proceedings:2014_igorr16:sergiopapadakis.docx |Analysis of a Loss of Offsite Power Event for the RA-10 Reactor}}                                                                                                                           S. Papadakis                                     | 
- Characterization of UO2-Gd2O3 nuclear fuel obtained by co-precipitation by Transmission Electron Microscopy I. Gana Document  +| {{ :proceedings:2014_igorr16:robertomaturana.docx |Analysis of an Inadvertent Control Plate Withdrawal Event in the RA-10 Reactor}}                                                                                                            | R. Maturana                                      | 
- CNEA DEVELOPMENTS IN U-Mo-Zry-4 MINIPLATES AND PLATES CO-ROLLING CONTROL B. Picchetti Document  +| {{ :proceedings:2014_igorr16:full_igorr2014_hikim_eog_051.doc |Analysis on LCO for On-Power Loading/Unloading Irradiation Targets in a Research Reactor}}                                                                                      | Hyeonil Kim                                      | 
- COCONEUT: An innovative deterministic neutronic calculation tool for research reactors J.-G. Lacombe Document  +| {{ :proceedings:2014_igorr16:mariogramajo.pdf |CFD Models of the RA-10 RI Facilities: A Useful Tool for Design Support}}                                                                                                                       M. Gramajo                                       | 
- Conceptual Design of a Compact Nuclear Reactor Core R.Vignolo Document  +| {{ :proceedings:2014_igorr16:ignacioganawatkins1.docx |Characterization of UO2-Gd2O3 nuclear fuel obtained by co-precipitation by Transmission Electron Microscopy}}                                                                           I. Gana                                          | 
- Conceptual Design of a Research Reactor with Monolithic UMo Fuels J.I. Beliera Document  +| {{ :proceedings:2014_igorr16:biancapicchetti.docx |CNEA DEVELOPMENTS IN U-Mo-Zry-4 MINIPLATES AND PLATES CO-ROLLING CONTROL}}                                                                                                                  | B. Picchetti                                     | 
- Conceptual Design of the Core of an ADS (Accelerator Driven System) M. Tacca Document  +| {{ :proceedings:2014_igorr16:jeangaellacombe1.doc |COCONEUT: An innovative deterministic neutronic calculation tool for research reactors}}                                                                                                    | J.-G. Lacombe                                    | 
- Contributions of CFD to the analysis of the second shutdown system of the RA-10 research reactor L. M. Rechiman Document  +| {{ :proceedings:2014_igorr16:ramirovignolo.doc |Conceptual Design of a Compact Nuclear Reactor Core}}                                                                                                                                          | R.Vignolo                                        | 
- Correction factors to apply to fission rates measured by miniature fission chambers in various neutron spectra B. Geslot Document  +| {{ :proceedings:2014_igorr16:juanbeliera.pdf |Conceptual Design of a Research Reactor with Monolithic UMo Fuels}}                                                                                                                              | J.I. Beliera                                     | 
- Creativity in Cold Neutron Sources Design L. Manifacier Document  +| {{ :proceedings:2014_igorr16:tacca.pdf |Conceptual Design of the Core of an ADS (Accelerator Driven System)}}                                                                                                                                  | M. Tacca                                         | 
- CURRENT STATUS OF JRR-3 Y. Kashima Document  +| {{ :proceedings:2014_igorr16:rechiman_paper_igorr2014_v2.doc |Contributions of CFD to the analysis of the second shutdown system of the RA-10 research reactor}}                                                                               L. M. Rechiman                                   | 
- Current Status of the KJRR Project and its Design Features C.Park Document  +| {{ :proceedings:2014_igorr16:benoitgeslot.pdf |Correction factors to apply to fission rates measured by miniature fission chambers in various neutron spectra}}                                                                                | B. Geslot                                        | 
- Cyber Security Study for Research Reactors J. Shin Document  +| {{ :proceedings:2014_igorr16:laurentmanifacier.doc |Creativity in Cold Neutron Sources Design}}                                                                                                                                                | L. Manifacier                                    | 
- Density determination of pyrotechnical devices using neutron imaging techniques on the RA-6 reactor N. Chiaraviglio Document  +| {{ :proceedings:2014_igorr16:kashima.pdf |CURRENT STATUS OF JRR-3}}                                                                                                                                                                            | Y. Kashima                                       | 
- DEPLETION ANALYSIS OF THE OPAL REACTOR WITH VESTA P.Young Document  +| {{ :proceedings:2014_igorr16:kjrr-project.pdf |Current Status of the KJRR Project and its Design Features}}                                                                                                                                    | C.Park                                           | 
- Description and Applications of the Neutron Imaging Facility at RA-6 J. Marin Document  +| {{ :proceedings:2014_igorr16:shin.doc |Cyber Security Study for Research Reactors}}                                                                                                                                                            | J. Shin                                          | 
- 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  +| {{ :proceedings:2014_igorr16:nicolas-chiaraviglio.docx |Density determination of pyrotechnical devices using neutron imaging techniques on the RA-6 reactor}}                                                                                  | N. Chiaraviglio                                  | 
- Design of a calibration beam for detector characterization J. M. Longhino Document  +| {{ :proceedings:2014_igorr16:opal-perryyoung.pdf |DEPLETION ANALYSIS OF THE OPAL REACTOR WITH VESTA}}                                                                                                                                          | P.Young                                          | 
- Development of Emergency Operating Guidelines for a Research Reactor Hyeonil Kim Document  +| {{ :proceedings:2014_igorr16:juliomar.docx |Description and Applications of the Neutron Imaging Facility at RA-6}}                                                                                                                             J. Marin                                         | 
- Development of Equipment for Simulating Coolant Flow in a Test Rig J. T. Hong Document  +| {{ :proceedings:2014_igorr16:bendotti-neyroud.pdf |Design and first operation of the DIAMINO (U241AmO2) experiment in OSIRIS MTR for Am-recycling program}}                                                                                    | S. BENDOTTI, C. NEYROUD, S. BEJAOUI, T. LAMBERT  | 
- Development of Laser Welding Technology for Fabricating Nuclear Fuel Test Rig C.Y. Joung Document  +| {{ :proceedings:2014_igorr16:juanlonghino.docx |Design of a calibration beam for detector characterization}}                                                                                                                                   J. M. Longhino                                   | 
- Development of Safety Management Portal System for HANARO Research Reactor Hoan Sung Jung Document  +| {{ :proceedings:2014_igorr16:full_igorr2014_hikim_eog.doc |Development of Emergency Operating Guidelines for a Research Reactor}}                                                                                                              | Hyeonil Kim                                      | 
- Deviation from ASME III Code rules for the design of Research Reactors M. Wesley Document  +| {{ :proceedings:2014_igorr16:jintaehong.docx |Development of Equipment for Simulating Coolant Flow in a Test Rig}}                                                                                                                             J. T. Hong                                       | 
- 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  +| {{ :proceedings:2014_igorr16:chang-young-1.docx |Development of Laser Welding Technology for Fabricating Nuclear Fuel Test Rig}}                                                                                                               C.Y. Joung                                       | 
- Dog-Bone Studies In U-Mo-Zry-4 Miniplates Fabrication Process M. Lopez Document  +| {{ :proceedings:2014_igorr16:hsjung-igorr2014-final.doc |Development of Safety Management Portal System for HANARO Research Reactor}}                                                                                                          | Hoan Sung Jung                                   | 
- Education and Training at Low Power Research Reactor VR-1 for National and International Students and Trainees Lubomir Sklenka -  Czech Republic Document  +| {{ :proceedings:2014_igorr16:wesley.docx |Deviation from ASME III Code rules for the design of Research Reactors}}                                                                                                                             M. Wesley                                        | 
- ENEA Thermal and Fast Research Reactors utilization for R&D activities at Casaccia Center M. Sepielli Document  +| {{ :proceedings:2014_igorr16:zampa.doc |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                                       | 
- Expansion of the Cold Neutron Facilities and Reactor Upgrades at the NIST Center for Neutron Research R. E. Williams Document  +| {{ :proceedings:2014_igorr16:lopez-picchetti.doc |Dog-Bone Studies In U-Mo-Zry-4 Miniplates Fabrication Process}}                                                                                                                              | M. Lopez                                         | 
- Experimental Investigation of Operational Parameters in the CDTN TRIGA Reactor A.Z Mesquita Document  +| {{ :proceedings:2014_igorr16:lubomirsklenka1.doc |Education and Training at Low Power Research Reactor VR-1 for National and International Students and Trainees}}                                                                             Lubomir Sklenka -  Czech Republic                | 
- Experimental Study on Downward Two-Phase Flow in Vertical Narrow Rectangular Channel J.H. Jeong Document  +| {{ :proceedings:2014_igorr16:massimo-sepielli.doc |ENEA Thermal and Fast Research Reactors utilization for R&D activities at Casaccia Center}}                                                                                                 M. Sepielli                                      | 
- FPGA Based Reactor Protection System Architecture C.A. Verrastro Document  +| {{ :proceedings:2014_igorr16:robertwilliams.docx |Expansion of the Cold Neutron Facilities and Reactor Upgrades at the NIST Center for Neutron Research}}                                                                                      | R. E. Williams                                   | 
- FRM II: Results and experience of the major maintenance shutdown after ten years of operation A. Pichlmaier Document  +| {{ :proceedings:2014_igorr16:amir-mesquita1.doc |Experimental Investigation of Operational Parameters in the CDTN TRIGA Reactor}}                                                                                                              | A.Z Mesquita                                     | 
- Heat Deposition in Out-Core Devices of Research Reactors after Actuation of a Shutdown System Based on Reflector Tank Draining H. Meier Document  +| {{ :proceedings:2014_igorr16:jihwanjeong.doc |Experimental Study on Downward Two-Phase Flow in Vertical Narrow Rectangular Channel}}                                                                                                           J.H. Jeong                                       | 
- High Order Finite Elements for Reactor Calculation. Examples and Comparison with Experimental Results Carlos R. Grant Document  +| {{ :proceedings:2014_igorr16:claudioverrastro.doc |FPGA Based Reactor Protection System Architecture}}                                                                                                                                         C.A. Verrastro                                   | 
- Implementation and Utilization of Positron Annihilation Spectrometry Methods at the PULSTAR Reactor A. I. Hawari Document  +| {{ :proceedings:2014_igorr16:axelpichlmaier.pdf |FRM II: Results and experience of the major maintenance shutdown after ten years of operation}}                                                                                               A. Pichlmaier                                    | 
- Implementation of a Periodic Safety Review of HANARO Research Reactor Minjin Kim Document  +| {{ :proceedings:2014_igorr16:meir.docx |Heat Deposition in Out-Core Devices of Research Reactors after Actuation of a Shutdown System Based on Reflector Tank Draining}}                                                                       H. Meier                                         | 
- Implementation of the Neutron Noise Technique for Measurement of Reactivity in Subcritical of the Low Power Research Reactor RA-4 J. Orso Document  +| {{ :proceedings:2014_igorr16:carlosgrant.doc |High Order Finite Elements for Reactor Calculation. Examples and Comparison with Experimental Results}}                                                                                          | Carlos R. Grant                                  | 
- IMPROVING IMMUNITY OF THE OPAL REACTOR TO ELECTRICAL POWER DISTURBANCES B. GITTOES Document  +| {{ :proceedings:2014_igorr16:hawari_ncsu_paper_02.docx |Implementation and Utilization of Positron Annihilation Spectrometry Methods at the PULSTAR Reactor}}                                                                                  | A. I. Hawari                                     | 
- Instrumentation & Control Systems for the Brazilian Multipurpose Reactor - RMB P. Carvalho Document  +| {{ :proceedings:2014_igorr16:minjin.doc |Implementation of a Periodic Safety Review of HANARO Research Reactor}}                                                                                                                               Minjin Kim                                       | 
- Integral (n,y) Cross-sections Measurement of Standard Light Water Reactors Materials A. Gruel Document  +| {{ :proceedings:2014_igorr16:joseorso.doc |Implementation of the Neutron Noise Technique for Measurement of Reactivity in Subcritical of the Low Power Research Reactor RA-4}}                                                                 J. Orso                                          | 
- Investigation of Mixed Enrichment Core Loadings for the PULSTAR Reactor A. I. Hawari Document  +| {{ :proceedings:2014_igorr16:gittoes.docx |IMPROVING IMMUNITY OF THE OPAL REACTOR TO ELECTRICAL POWER DISTURBANCES}}                                                                                                                           B. GITTOES                                       | 
- IRRADIATION CAPSULE DESIGN TO SUPPORT DOE RESUMPTION OF US 60Co ISOTOPE PRODUCTION R. Howard Document  +| {{ :proceedings:2014_igorr16:paulocarvalho.doc |Instrumentation & Control Systems for the Brazilian Multipurpose Reactor - RMB}}                                                                                                               P. Carvalho                                      | 
- Irradiation Facilities Performance at RA-10 F. Sanchez Document  +| {{ :proceedings:2014_igorr16:gruel.docx |Integral (n,y) Cross-sections Measurement of Standard Light Water Reactors Materials}}                                                                                                                | A. Gruel                                         | 
- Irradiation Loop Facility in RA-10 Reactor L. Vazquez Document  +| {{ :proceedings:2014_igorr16:hawari01.docx |Investigation of Mixed Enrichment Core Loadings for the PULSTAR Reactor}}                                                                                                                          | A. I. Hawari                                     | 
- Irradiation Requirements for Radioisotope Production D. Hergenreder Document  +| {{ :proceedings:2014_igorr16:richard-howard.docx |IRRADIATION CAPSULE DESIGN TO SUPPORT DOE RESUMPTION OF US 60Co ISOTOPE PRODUCTION}}                                                                                                         R. Howard                                        | 
- JULES HOROWITZ REACTOR OPERATION IN MOCK-UP MODES J. Estrade Document  +| {{ :proceedings:2014_igorr16:fernandosanchez.docx |Irradiation Facilities Performance at RA-10}}                                                                                                                                               F. Sanchez                                       | 
- Jules Horowitz Reactor: organization for the preparation of the commissioning phase and normal operation J. Estrade Document  +| {{ :proceedings:2014_igorr16:luisvazquez.docx |Irradiation Loop Facility in RA-10 Reactor}}                                                                                                                                                    | L. Vazquez                                       | 
- Kinetic Parameters Estimation in the RA-0 Research Reactor P. Bellino Document  +| {{ :proceedings:2014_igorr16:d-hergenreder.docx |Irradiation Requirements for Radioisotope Production}}                                                                                                                                        | D. Hergenreder                                   | 
- LEVEL 1 PROBABILISTIC SAFETY ASSESSMENT FOR LICENSING OF RA-10 REACTOR M. Grinberg Document  +| {{ :proceedings:2014_igorr16:j-estrade-mockup.doc |JULES HOROWITZ REACTOR OPERATION IN MOCK-UP MODES}}                                                                                                                                         J. Estrade                                       | 
- LEVEL 2 AND 3 PROBABILISTIC SAFETY ASSESSMENT FOR LICENSING OF RA-10 REACTOR C. Mulleady Document  +| {{ :proceedings:2014_igorr16:j-estrade-commisionning.doc |Jules Horowitz Reactor: organization for the preparation of the commissioning phase and normal operation}}                                                                           J. Estrade                                       | 
- LORELEI: A future Test Device for LOCA Experiments in the JHR L. Ferry Document  +| {{ :proceedings:2014_igorr16:pablobellino01.doc |Kinetic Parameters Estimation in the RA-0 Research Reactor}}                                                                                                                                  | P. Bellino                                       | 
- Materials Surveillance Programme for the RA10 Research Reactor R. Versaci Document  +| {{ :proceedings:2014_igorr16:marielagrinberg.doc |LEVEL 1 PROBABILISTIC SAFETY ASSESSMENT FOR LICENSING OF RA-10 REACTOR}}                                                                                                                     M. Grinberg                                      | 
- Measurement of Fission Products and Chemical Species released by Experimental Samples irradiated in the Jules Horowitz Reactor D. Parrat Document  +| {{ :proceedings:2014_igorr16:cristmulleady.doc |LEVEL 2 AND 3 PROBABILISTIC SAFETY ASSESSMENT FOR LICENSING OF RA-10 REACTOR}}                                                                                                                 C. Mulleady                                      | 
- Measurement of the Xenon-135 Reactivity Evolution after a Shutdown in the RA-3 Research and Production Reactor P. Bellino Document  +| {{ :proceedings:2014_igorr16:lionelferry.doc |LORELEI: A future Test Device for LOCA Experiments in the JHR}}                                                                                                                                  | L. Ferry                                         | 
- Mechanicals description of RA-10 Reactor and Service Pool and main Core Components A. Coleff Document  +| {{ :proceedings:2014_igorr16:raul-versaci.docx |Materials Surveillance Programme for the RA10 Research Reactor}}                                                                                                                               R. Versaci                                       | 
- 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  +| {{ :proceedings:2014_igorr16:danielparrat.docx |Measurement of Fission Products and Chemical Species released by Experimental Samples irradiated in the Jules Horowitz Reactor}}                                                               D. Parrat                                        | 
- Neutron Absorbing Glass Microspheres as Second Shutdown System I. Gana Document  +| {{ :proceedings:2014_igorr16:pablobellino02.docx |Measurement of the Xenon-135 Reactivity Evolution after a Shutdown in the RA-3 Research and Production Reactor}}                                                                             P. Bellino                                       | 
- Neutron and Gamma Shielding Design of the Neutron Guide Primary Shutter in a Research Reactor A. Maître Document  +| {{ :proceedings:2014_igorr16:coleff.doc |Mechanicals description of RA-10 Reactor and Service Pool and main Core Components}}                                                                                                                  | A. Coleff                                        | 
- Neutron Cold Source Optimization for RA-10 reactor A. Marquez Document  +| {{ :proceedings:2014_igorr16:cathalau.doc |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 Flux and Reactor Kinetic parameters Calculations in the RA0 Reactor L. Romero Document  +| {{ :proceedings:2014_igorr16:ignacioganawatkins2.docx |Neutron Absorbing Glass Microspheres as Second Shutdown System}}                                                                                                                        | I. Gana                                          | 
- Neutronic Analysis of the Jamaican SLOWPOKE-2 Research Reactor for the Conversion from HEU to LEU Fuel H. Dennis Document  +| {{ :proceedings:2014_igorr16:alexismaitre.doc |Neutron and Gamma Shielding Design of the Neutron Guide Primary Shutter in a Research Reactor}}                                                                                                 A. Maître                                        | 
- Neutronic Calculation Methodology for Research Reactors E. Villarino Document  +| {{ :proceedings:2014_igorr16:arielmarquez.doc |Neutron Cold Source Optimization for RA-10 reactor}}                                                                                                                                            | A. Marquez                                       | 
- Neutronic Design of the RA10 Research Reactor´s Core J.M.Tunon Document  +| {{ :proceedings:2014_igorr16:luisromero-cbarberis.doc |Neutron Flux and Reactor Kinetic parameters Calculations in the RA0 Reactor}}                                                                                                           L. Romero                                        | 
- Neutronic Design of the RMB Research Reactor J.M.Tunon Document  +| {{ :proceedings:2014_igorr16:haile-dennis.docx |Neutronic Analysis of the Jamaican SLOWPOKE-2 Research Reactor for the Conversion from HEU to LEU Fuel}}                                                                                       H. Dennis                                        | 
- Neutronic Simulation of IPR-R1 TRIGA First Configuration using Serpent and MCNP Codes S. P. de Meireles Document  +| {{ :proceedings:2014_igorr16:eduardo-villarino.docx |Neutronic Calculation Methodology for Research Reactors}}                                                                                                                                 E. Villarino                                     | 
- New Core with Low-Enriched Uranium Fuel at the Kazakhstan Critical Facility A. Shaimerdenov Document  +| {{ :proceedings:2014_igorr16:juantunon-ra10.docx |Neutronic Design of the RA10 Research Reactor´s Core}}                                                                                                                                       J.M.Tunon                                        | 
- Nuclear Education & Training activity experience at the University of Pavia A. Salvini Document  +| {{ :proceedings:2014_igorr16:juantunon-rmb.docx |Neutronic Design of the RMB Research Reactor}}                                                                                                                                                | J.M.Tunon                                        | 
- Nuclear Instrumentation System of RA-10 G. Quesada Document  +| {{ :proceedings:2014_igorr16:peixoto-de-meireles.doc |Neutronic Simulation of IPR-R1 TRIGA First Configuration using Serpent and MCNP Codes}}                                                                                                  | S. P. de Meireles                                | 
- Numerical Investigation of Cooling in the Pool of the Brazilian Multipurpose Reactor (RMB) A.Z Mesquita Document  +| {{ :proceedings:2014_igorr16:shaimerdenov.doc |New Core with Low-Enriched Uranium Fuel at the Kazakhstan Critical Facility}}                                                                                                                   A. Shaimerdenov                                  | 
- OPAL Reactor Full 3-D Calculations using the MonteCarlo Code Serpent 2 Diego Ferraro Document  +| {{ :proceedings:2014_igorr16:andreasalvini.docx |Nuclear Education & Training activity experience at the University of Pavia}}                                                                                                                 A. Salvini                                       | 
- Operation and Utilisation of Low Power Research Reactor Critical Facility for Advanced Heavy Water Reactor (AHWR) S. K. De Document  +| {{ :proceedings:2014_igorr16:gonzaloquesada.doc |Nuclear Instrumentation System of RA-10}}                                                                                                                                                     G. Quesada                                       | 
- OPERATION, MAINTENANCE EXPERIENCE AND FUTURE CHALLENGES OF TRIGA RESEARCH REACTOR OF BANGLADESH M. A. Salam Document  +| {{ :proceedings:2014_igorr16:amir-mesquita2.doc |Numerical Investigation of Cooling in the Pool of the Brazilian Multipurpose Reactor (RMB)}}                                                                                                  | A.Z Mesquita                                     | 
- Optimisation Approach to Asses Seismic Reinforcements of a Low Power Research Reactor M. Auzas Document  +| {{ :proceedings:2014_igorr16:ferraro-villarino.docx |OPAL Reactor Full 3-D Calculations using the MonteCarlo Code Serpent 2}}                                                                                                                  | Diego Ferraro                                    | 
- PARCS Few-group Homogenized Parameters Generation using Serpent Monte Carlo code at the CROCUS Reactor A. Rais Document  +| {{ :proceedings:2014_igorr16:skde.docx |Operation and Utilisation of Low Power Research Reactor Critical Facility for Advanced Heavy Water Reactor (AHWR)}}                                                                                    | S. K. De                                         | 
- Preliminary Studies on A New Research Reactor and Cold Neutron Source at NIST Zeyun Wu Document  +| {{ :proceedings:2014_igorr16:salam.docx |OPERATION, MAINTENANCE EXPERIENCE AND FUTURE CHALLENGES OF TRIGA RESEARCH REACTOR OF BANGLADESH}}                                                                                                     M. A. Salam                                      | 
- Preparation and Submission of a Manuscript for the Proceedings of the Technical Meeting A. Malaquias Document  +| {{ :proceedings:2014_igorr16:auzas.doc |Optimisation Approach to Asses Seismic Reinforcements of a Low Power Research Reactor}}                                                                                                                | M. Auzas                                         | 
- Production Facilities for Reactor Produced Radioisotopes J. Merino Document  +| {{ :proceedings:2014_igorr16:adolforais-crocus.pdf |PARCS Few-group Homogenized Parameters Generation using Serpent Monte Carlo code at the CROCUS Reactor}}                                                                                   A. Rais                                          | 
- RA10 - Utilization-driven Layout N. De Lorenzo Document  +| {{ :proceedings:2014_igorr16:zeyunwu.pdf |Preliminary Studies on A New Research Reactor and Cold Neutron Source at NIST}}                                                                                                                      | Zeyun Wu                                         | 
- RA-10 Design Management: Strategic Objectives and Specific Actions F. Brollo Document  +| {{ :proceedings:2014_igorr16:silvanaperalta.doc |Preparation and Submission of a Manuscript for the Proceedings of the Technical Meeting}}                                                                                                     A. Malaquias                                     | 
- RA-10 Project Safety Assessment and Licensing Process P. Ramirez Document  +| {{ :proceedings:2014_igorr16:juanmerino.docx |Production Facilities for Reactor Produced Radioisotopes}}                                                                                                                                       J. Merino                                        | 
- Relevant Characteristics of the RA-10 I&C Systems P. Cantero Document  +| {{ :proceedings:2014_igorr16:nestordelorenzo.docx |RA10 - Utilization-driven Layout}}                                                                                                                                                          | N. De Lorenzo                                    | 
- Relicensing of the SM1 Sub-critical assembly of the Pavia University L. Strada Document  +| {{ :proceedings:2014_igorr16:fabricio-brollo.pdf |RA-10 Design Management: Strategic Objectives and Specific Actions}}                                                                                                                         F. Brollo                                        | 
- Renovation, improvement and experimental validation of the Helium-3 transient rods system for the reactivity injection in the CABRI reactor B. Duc Document  +| {{ :proceedings:2014_igorr16:pabloramirez.doc |RA-10 Project Safety Assessment and Licensing Process}}                                                                                                                                         P. Ramirez                                       | 
- Replacement of the Oregon State University TRIGA® Reactor Annular Reflector S. Todd Keller Document  +| {{ :proceedings:2014_igorr16:cantero.pdf |Relevant Characteristics of the RA-10 I&C Systems}}                                                                                                                                                  | P. Cantero                                       | 
- Research Institute of Atomic Reactors D. Fomin Document  +| {{ :proceedings:2014_igorr16:strada.docx |Relicensing of the SM1 Sub-critical assembly of the Pavia University}}                                                                                                                               L. Strada                                        | 
- Research Reactor Spent Fuel Management in Argentina L. Mottillo Document  +| {{ :proceedings:2014_igorr16:duc.docx |Renovation, improvement and experimental validation of the Helium-3 transient rods system for the reactivity injection in the CABRI reactor}}                                                           B. Duc                                           | 
- Review of low-power research reactor developed for education and training In-Cheol Lim - Korea Document  +| {{ :proceedings:2014_igorr16:keller.doc |Replacement of the Oregon State University TRIGA® Reactor Annular Reflector}}                                                                                                                         S. Todd Keller                                   | 
- RMB: THE NEW BRAZILIAN MULTIPURPOSE RESEARCH REACTOR J.A. Perrotta Document  +| {{ :proceedings:2014_igorr16:lubomirsklenka1.doc |Research Institute of Atomic Reactors}}                                                                                                                                                      | D. Fomin                                         | 
- Simplified Method For Thermal-Hydraulic Design And Evaluation Of Research Reactor Core, Coupled With Neutronic Montecarlo Calculation M.A.N Giménez Document  +| {{ :proceedings:2014_igorr16:leonardomottillo.doc |Research Reactor Spent Fuel Management in Argentina}}                                                                                                                                       L. Mottillo                                      | 
- SIREx: Instrumentation System for Research Reactors F.D. Rossi Mescolatti Document  +| {{ :proceedings:2014_igorr16:lim.doc |Review of low-power research reactor developed for education and training}}                                                                                                                              | In-Cheol Lim - Korea                             | 
- Start-up of a New Storage Facility for Spent Fuel from Research Reactors at CNEA O. Novara Document  +| {{ :proceedings:2014_igorr16:joseperrotta.doc |RMB: THE NEW BRAZILIAN MULTIPURPOSE RESEARCH REACTOR}}                                                                                                                                          | J.A. Perrotta                                    | 
- Status of uranium targets irradiation in MARIA reactor for molybdenum production G. Krzysztoszek Document  +| {{ :proceedings:2014_igorr16:gimenez.doc |Simplified Method For Thermal-Hydraulic Design And Evaluation Of Research Reactor Core, Coupled With Neutronic Montecarlo Calculation}}                                                              | M.A.N Giménez                                    | 
- The Enhancement of VR-1 Reactor Utilization for Practical Education Using Portable Neutron Generator J. Rataj Document  +| {{ :proceedings:2014_igorr16:federicorossi1.pdf |SIREx: Instrumentation System for Research Reactors}}                                                                                                                                         F.D. Rossi Mescolatti                            | 
- The IPEN/MB-01 zero power reactor and the LABGENE reactor experimental programme P. Piovezan Document  +| {{ :proceedings:2014_igorr16:oscarnovara.doc |Start-up of a New Storage Facility for Spent Fuel from Research Reactors at CNEA}}                                                                                                               O. Novara                                        | 
- 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  +| {{ :proceedings:2014_igorr16:krzysztoszek.docx |Status of uranium targets irradiation in MARIA reactor for molybdenum production}}                                                                                                             G. Krzysztoszek                                  | 
- The RMB Research Reactor Project C. Mazufri Document  +| {{ :proceedings:2014_igorr16:janrataj.pdf |The Enhancement of VR-1 Reactor Utilization for Practical Education Using Portable Neutron Generator}}                                                                                              | J. Rataj                                         | 
- Thermal-Hydraulic Aspects for the Upgrade of a Research Reactor C. Pavon Document  +| {{ :proceedings:2014_igorr16:pamelapiovezan.doc |The IPEN/MB-01 zero power reactor and the LABGENE reactor experimental programme}}                                                                                                            | P. Piovezan                                      | 
- Thermal-hydraulic aspects of RMB design J. Lupiano Contreras Document  +| {{ :proceedings:2014_igorr16:bignan.docx |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                                        | 
- TRACE Code Application to Low Operating Pressure Research Reactor Safety Analysis A. Rais Document  +| {{ :proceedings:2014_igorr16:claudio_mazufri.doc |The RMB Research Reactor Project}}                                                                                                                                                           C. Mazufri                                       | 
- Trace element Content of Zingiber Officinalis and Salvia Officinalis plants from Algeria Z.Lamari Document  +| {{ :proceedings:2014_igorr16:carlospavon.doc |Thermal-Hydraulic Aspects for the Upgrade of a Research Reactor}}                                                                                                                                | C. Pavon                                         | 
- Transmutation Experimental Facility for Research and Development of Accelerator-Driven System in JAEA K. Tsujimoto Document  +| {{ :proceedings:2014_igorr16:jorgelinalupianocontreras.doc |Thermal-hydraulic aspects of RMB design}}                                                                                                                                          | J. Lupiano Contreras                             | 
- Use of Pulse-Mode Neutron Flux-Change-Rate as a Trip Condition in a Nuclear Reactor F.N. Ferrucci Document  +| {{ :proceedings:2014_igorr16:adolforais.pdf |TRACE Code Application to Low Operating Pressure Research Reactor Safety Analysis}}                                                                                                               A. Rais                                          | 
- Use Virtual Environments for Training in Nuclear Facilities P. Carvalho Document  +| {{ :proceedings:2014_igorr16:zohralamari.pdf |Trace element Content of Zingiber Officinalis and Salvia Officinalis plants from Algeria}}                                                                                                       Z.Lamari                                         | 
- Utilization of the Dalat Research Reactor After Its Core Conversion N. Nhi Dien Document  +| {{ :proceedings:2014_igorr16:tsujimoto.doc |Transmutation Experimental Facility for Research and Development of Accelerator-Driven System in JAEA}}                                                                                            | K. Tsujimoto                                     | 
- Utilization of the High Flux Isotope Reactor at Oak Ridge National Laboratory D. L. Selby Document  +| {{ :proceedings:2014_igorr16:ferrucci.doc |Use of Pulse-Mode Neutron Flux-Change-Rate as a Trip Condition in a Nuclear Reactor}}                                                                                                               F.N. Ferrucci                                    | 
- Utilization, Safety and Aging Management of the High Flux Isotope Reactor at Oak Ridge National Laboratory R. A. Crone Document  +| {{ :proceedings:2014_igorr16:paulocarvalho2.doc |Use Virtual Environments for Training in Nuclear Facilities}}                                                                                                                                 P. Carvalho                                      | 
- Wide Range Amplifier for Neutron Flux Measurement L. Giuliodori Document +| {{ :proceedings:2014_igorr16:nguyennhidien.doc |Utilization of the Dalat Research Reactor After Its Core Conversion}}                                                                                                                          | N. Nhi Dien                                      | 
 +| {{ :proceedings:2014_igorr16:douglasselbyigorr.docx |Utilization of the High Flux Isotope Reactor at Oak Ridge National Laboratory}}                                                                                                           D. L. Selby                                      | 
 +| {{ :proceedings:2014_igorr16:croneronald.pdf |Utilization, Safety and Aging Management of the High Flux Isotope Reactor at Oak Ridge National Laboratory}}                                                                                     R. A. Crone                                      | 
 +| {{ :proceedings:2014_igorr16:luisgiuliodori.docx |Wide Range Amplifier for Neutron Flux Measurement}}                                                                                                                                          | L. Giuliodori                                    | 
 +</datatables>
proceedings/2014_igorr16.1703745924.txt.gz · Last modified: 2023/12/28 07:45 by Joerg Pulz

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