proceedings:2017_igorr18
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| proceedings:2017_igorr18 [2023/12/29 11:56] – start linkify Joerg Pulz | proceedings:2017_igorr18 [2023/12/29 15:09] (current) – datatables Joerg Pulz | ||
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| - | | IGORR - IAEA Joint Conference | + | ^ Title ^ Author(s) |
| - | | opening presentation | + | | {{ : |
| - | | 2 IGORR18-CEA-ICERR-Sydney-December 2017 | Gilles Bignan | + | | {{ : |
| - | | Establishing the conditions for successful implementation of public private partnerships | + | | {{ : |
| - | | RIAR as IAEA ICERR : Pilot Technical Cooperation Projects and Future Prospects | + | | {{ : |
| - | | Long Term Operation of the Advanced Test Reactor | + | | {{ : |
| - | | IAEA Activities to Support Sustainable Operation of and Access to Research Reactors | + | | {{ : |
| - | | Present Status of Kyoto University Research Reactor, KUR | Ken Nakajima | + | | {{ : |
| - | | Some thoughts on operator intervention arising from safety reassessments of research reactors in the light of the Fukushima Daiichi NPP accident | + | | {{ : |
| - | | IAEA Activities on Safety of Research Reactors | + | | {{ : |
| - | | Implementation of the post-Fukushima Daiichi accident Enhancement Programme for RRs | + | | {{ : |
| - | | Implementation of lessons learned from the Fukushima Dai-ichi accident Research Reactors | + | | {{ : |
| - | | New Safety Requirements Addressing Feedback From the Fukushima Daiichi Accident | + | | {{ : |
| - | | Disposing high-level tranuranic waste in subcritical reactors | + | | {{ : |
| - | | The Jules Horowitz Research Reactor Experimental devices and first orientations for the experimental programs | + | | {{ : |
| - | | Commissioning of the Jordan Research and Training Reactor | + | | {{ : |
| - | | Completion of Jordan Research and Training Reactor Construction Project | + | | {{ : |
| - | | Contributions of previous projects to the design of new research reactors | + | | {{ : |
| - | | Ageing Management and SSC's Improvements at IRR1 | N. Hazenshprung | + | | {{ : |
| - | | The journey of Continuous Improvement in the Reliability and Availability of the OPAL Reactor | + | | {{ : |
| - | | The impact of changes in utilization on human performance | + | | {{ : |
| - | | Modeling and Simulation of Dispersion Particle Fuels in Monte Carlo Neutron Transport Calculation | + | | {{ : |
| - | | Observations of the Experimental Study of Fluid-Structure-Interactions of Plate-Type-Fuel | + | | {{ : |
| - | | Feasibility Studies for Simultaneous Irradiation of NBSR & MITR Fuel Elements in the BR2 Reactor | + | | {{ : |
| - | | Study of an Integrated Passive Safety System for a Research Reactor | + | | {{ : |
| - | | Safety Analysis For Prototype MNSR HEU Core Unloading And Storage | + | | {{ : |
| - | | Secure Enterprise Integration for Research Reactors | + | | {{ : |
| - | | First Periodic Safety Review of the FRM II after 10 years of routine operation | + | | {{ : |
| - | | Status of a Periodic Safety Review of HANARO | + | | {{ : |
| - | | MARIA reactor safety improvements and research capacity improvements | + | | {{ : |
| - | | Findings and results of safety reassessments and safety improvements on the ORPHEE research reactor | + | | {{ : |
| - | | Completion of Seismic Rehabilitation Project at HANARO after the Fukushima Daiichi Accident | + | | {{ : |
| - | | Safety Reassessment of German Research Reactors after the Accident at Fukushima Daiichi NPP | + | | {{ : |
| - | | Enhancement of the Safety of the Jordan Research and Training Reactor JRTR | Khalifeh AbuSaleem | + | | {{ : |
| - | | Assessment of Lessons Learned from the Fukushima Dai-ichiNuclear Accident to Research and Test Reactors in the United States | + | | {{ : |
| - | | JHR PROJECT irradation device in-service inspection of nuclear pressure equipment' | + | | {{ : |
| - | | Monte-Carlo coupled depletion codes efficiency for research reactor design | + | | {{ : |
| - | | Thermal-hydraulyc conceptual design of the new multipurpose research reactor succeeding to JRR-3 | Masaji Arai | New projects | + | | {{ : |
| - | | The construction stage in the RA-10 Reactor Project | + | | {{ : |
| - | | Resumption of Transient Testing Program TREAT Startup Update | + | | {{ : |
| - | | MOLY production in the Jules Horowitz Reactor capacity and status of the development | + | | {{ : |
| - | | Core Elements Improvements for Optimizationof Radioisotopes Production in an MTR-type Core | T. Makmal | + | | {{ : |
| - | | Production of Medical Isotopes at the FRM II Research Reactor | + | | {{ : |
| - | | MARIA reactor for medecine nuclear and material research | + | | {{ : |
| - | | Competence Development Of Research Reactors Personnel in Indonesia | + | | {{ : |
| - | | The new materail iradiation infrastructure at the BR2 reactor | + | | {{ : |
| - | | Current and Prospective Tests in Reactor MIR.M1 | + | | {{ : |
| - | | Radiation Safety Training at the Open Pool Australian Lightwater (OPAL) Multipurpose Reactor | + | | {{ : |
| - | | TAPIRO fast spectrum research reactor for neutron radiation damage analyses | + | | {{ : |
| - | | The IAEA Internet Reactor Laboratory project | + | | {{ : |
| - | | Safety reassessment of Egyptian second research reactor post Fukushima accident ETRR-2 | + | | {{ : |
| - | | Post Fukushima safety assessment of the Hungarian research reactor | + | | {{ : |
| - | | Safety Enhancement of Dhruva Reactor through Periodic Safety Review (PSR) | + | | {{ : |
| - | | Safety Reevaluation of Indonesian MTR-Type Research Reactor | + | | {{ : |
| - | | CIAE Thermal Hydraulic Analysis of 49-2 Swimming Pool Reactor with a Passive Siphon Breaker | + | | {{ : |
| - | | Kazakhstan-Safety reassessment of WWR-K RR related to HEU/LEU conversion and feedback from accident at the Fukushima-Daiichi NPP | Murat Tulegenov | + | | {{ : |
| - | | Internal peer review (IPR) of Pakistan Research Reactor-1 (PARR-1) | + | | {{ : |
| - | | Safety Reassessment of MARIA research reactor in Poland | + | | {{ : |
| - | | SAFARI-1 Safety reassessment and modifications in light of Fukushima Daiichi accident | + | | {{ : |
| - | | Identification and implementation of a hardened (safety) core in a research reactor in light of the lessons learned from the Fukushima Daiichi accident. The JHR case. | Gilbert Rouvière | + | | {{ : |
| - | | Introduction of Nation-wide inspection and Reassessment to Chinese Research Reactors after Fukushima Accident | + | | {{ : |
| - | | Safety assessments of the Tehran research reactor (TRR) AEOI, NSTRI | + | | {{ : |
| - | | Safety reassessmants and actions taken in HANARO since Fukushima | + | | {{ : |
| - | | Experience with safety reviews of Slovenian Research Reactor by PSR and IAEA INSARR Missions and the stress tests for the Krsko NPP | + | | {{ : |
| - | | MIRION Technologies -RMS Division | + | | {{ : |
| - | | Validation of the Stable Period Method Against Analytic Solution | + | | {{ : |
| - | | Hydraulic design and validated calculation tools of the Jules Horowitz Reactor (JHR) Reflector | + | | {{ : |
| - | | Onset of Flow Instability in a Rectangular Channel Under Transversely Uniform And Non-uniform Heating | + | | {{ : |
| - | | Application of the next generation of the OSCAR code system to the ETRR-2 multi-cycle depletion benchmark | + | | {{ : |
| - | | Progress in Conceptual Research on Fusion Fission Hybrid Reactor for Energy (FFHR-E) | + | | {{ : |
| - | | RCC-MRx 2015 Context, overview and on-going developments | + | | {{ : |
| - | | The FIJHOP R&D program proposal | + | | {{ : |
| - | | RCC-MRx applicability for the design phase of experimental devices (JHR) | Sébastien Gay | New projects | + | | {{ : |
| - | | Commissioning Experience for Reactor and Primary Cooing System of Jordan Research and Training Reactor (JRTR) | + | | {{ : |
| - | | CNS In-pile Replacement Project Mk2 | + | | {{ : |
| - | | Cold Neutron Source (CNS) Helium Injection Logic Modification | + | | {{ : |
| - | | OPAL CNS Moderator Performance | + | | {{ : |
| - | | IAEA activities in support of operation and maintenance of research reactors | + | | {{ : |
| - | | Installation of a Second CLICIT Irradiation Facility at the Oregon State TRIGA Reactor | + | | {{ : |
| - | | Post irradiation testing capabilities of experimental reactor components at the LECI facility for service life assessment | + | | {{ : |
| - | | Power ramping and cycling testing of vver fuel rods in the MIR reactor | + | | {{ : |
| - | | Experimental Study of the VVER-1000 fuel rods behaviour under the design-basis RIA and LOCA in the MIR reactor | + | | {{ : |
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| - | | Installation of a Second CLICIT Irradiation Facility at the Oregon State TRIGA Reactor | + | | {{ : |
| - | | Progress in Conceptual Research on Fusion Fission Hybrid Reactor for energy | + | | {{ : |
| - | | Contributions of previous projects to the design of new research reactors | + | | {{ : |
| - | | POSSIBLE SHIFTS IN MARIA REACTOR REACTIVITY AND POWER CHANGES CAUSED BY THE SEISMIC EVENT | + | | {{ : |
| - | | Recent developments of the OSCAR calculational system, as applied to selected examples from IAEA research reactor benchmarks | + | | {{ : |
| - | | The CEA scientific and technical offer as a designated ICERR by the IAEA first feedback with the prime Affiliates | + | | {{ : |
| - | | Investigation on Core Downward Flow by a Passive Residual Heat Removal System of Research Reactor | + | | {{ : |
| - | | Investigation on Core Downward Flow by a Passive Residual Heat Removal System of Research Reactor | + | | {{ : |
| - | | Investigation of siphon breaker simulation program through small scale siphon breaker experiment | + | | {{ : |
| - | | Investigation of Siphon Breaker Simulation Program throught Small Scale Siphon Breaker Experiment | + | | {{ : |
| - | | Study of an Integrated Passive Safety System for a Research Reactor | + | | {{ : |
| - | | Abstract Findings and results of safety reassessments and safety improvements on the ORPHEE research reactor | + | | {{ : |
| - | | Hydraulic design and validated calculation tool of the Jules Horowitz Reactor Reflector | + | | {{ : |
| - | | Commissioning of the Jordan Research and Training Reactor (JRTR) | + | | {{ : |
| - | | Safety Analysis For Prototype MNSR HEU Core Unloading And Storage | + | | {{ : |
| - | | On-line Condition Monitoring Tool for Nuclear Research Reactors Coolant System Components | + | | {{ : |
| - | | JHR Project. Irradiation Devices In-Service Inspection of Nuclear Pressure Equipment’s Investigation of Non Destructive Examinations for inspection purposes | + | | {{ : |
| - | | Competence Development of Research Reactors Personnel in Indonesia | + | | {{ : |
| - | | Public Education and Outreach for Supporting Nuclear Program in Indonesia | + | | {{ : |
| - | | The new material irradiation infrastructure at the BR2 reactor | + | | {{ : |
| - | | Onset of Flow Instability in a Rectangular Channel Under Transversely Uniform and Non-uniform Heating | + | | {{ : |
| - | | Disposing High-level Transuranic Waste in Subcritical Reactors | + | | {{ : |
| - | | Application of the next generation of the OSCAR code system to the ETRR-2 multi-cycle depletion benchmark | + | | {{ : |
| - | | Monte-Carlo Coupled Depletion Codes Efficiency for Research Reactor Design | + | | {{ : |
| - | | A Dummy Core for V&V and Education & Training Purposes at TechnicAtome: | + | | {{ : |
| - | | Identification and implementation of a hardened core in a research reactor in light of the lessons learned from the Fukushima Daiichi accident. The JHR case | Gilbert Rouvière | + | | {{ : |
| - | | RCC-MRx 2015 CODE: CONTEXT, OVERVIEW AND ON-GOING DEVELOPMENTS | + | | {{ : |
| - | | Modification of the CNS Helium Injection Logic | Alfio Arcidiacono | + | | {{ : |
| - | | Analysis of a Hypothetical LOCA in an Open Pool Type Research Reactor | + | | {{ : |
| - | | OPAL Cold Neutron Source Moderator Performance | + | | {{ : |
| - | | Thermal-hydraulic conceptual design of the new multipurpose research reactor succeeding to JRR-3 | Masaji Arai | | + | | {{ : |
| - | | Multidisciplinary Engagement at Research Reactors : The NCSU PULSTAR | + | | {{ : |
| - | | Modeling and Simulation of Dispersion Particle Fuels in Monte Carlo Neutron Transport Calculation | + | | {{ : |
| - | | TAPIRO fast spectrum research reactor characteristics for neutron radiation damage analyses | + | | {{ : |
| - | | The FIJHOP R&D Program Proposal | + | | {{ : |
| - | | Present Status of Kyoto University Research Reactor, KUR | Ken Nakajima | + | | {{ : |
| - | | PRODUCTION OF MEDICAL RADIOISOTOPES AT THE FRM II RESEARCH REACTOR | + | | {{ : |
| - | | Observations on Experimental Fluid Structure Interactions of Plate-Type Fuel | W. Marcum | + | | {{ : |
| - | | THE IMPACT OF CHANGES IN UTILIZATION ON HUMAN PERFORMANCE | + | | {{ : |
| - | | Secure Enterprise Integration for Multipurpose Research Reactors | + | | {{ : |
| - | | JULES HOROWITZ REACTOR: RCC-MRx APPLICABILITY FOR THE DESIGN PHASE OF EXPERIMENTAL DEVICES | + | | {{ : |
| - | | FIRST PERIODIC SAFETY REVIEW OF THE FRM II AFTER 10 YEARS OF ROUTINE OPERATION | + | | {{ : |
| - | | Completion of Seismic Rehabilitation Project at HANARO after the Fukushima Daiichi Accident | + | | {{ : |
| - | | Status of a Periodic Safety Review of HANARO | + | | {{ : |
| - | | The IAEA Internet Reactor Laboratory project: status, feedback from recent broadcasting and future expansion | + | | {{ : |
| - | | The construction stage in the RA-10 Reactor Project | + | | {{ : |
| - | | Filling the Neutron Gap at the Canadian Nuclear Laboratories after Shutdown of the National Research Universal (NRU) Reactor | + | | {{ : |
| - | | Commissioning Experience for Reactor and Primary Cooing System of Jordan Research and Training Reactor (JRTR) | + | | {{ : |
| - | | EXPERIMENTAL DEVICES IN JULES HOROWITZ REACTOR AND FIRST ORIENTATIONS FOR THE EXPERIMENTAL PROGRAMS | + | | {{ : |
| - | | A qualitative study for establishing the conditions for the successful implementation of public private partnerships in research reactor project in newcomer countries | + | | {{ : |
| - | | The impact of cultural diversity on the technological innovation process in the nuclear energy corporations | + | | {{ : |
| - | | FEASIBILITY STUDIES FOR SIMULTANEOUS IRRADIATION OF NBSR & MITR FUEL ELEMENTS IN THE BR2 REACTOR | + | | {{ : |
| - | | Radioactive Radon Effect of Spent Fuel Storage Pool Kr-85 Monitor | + | | {{ : |
| - | | Radioactive Radon Effect of Spent Fuel Storage Pool Kr-85 Monitor 2 | + | | {{ : |
| - | | FEASIBILITY STUDIES FOR SIMULTANEOUS IRRADIATION OF NBSR & MITR FUEL ELEMENTS IN THE BR2 REACTOR | + | | {{ : |
| - | | Long Term Operation of the Advanced Test Reactor | + | | {{ : |
| - | | Completion of Jordan Research and Training Reactor Construction Project | + | | {{ : |
| - | | Power ramping and cycling testing of VVER fuel rods in the MIR reactor | + | | {{ : |
| - | | Experimental Study of the VVER-1000 Fuel Rods Behavior under the Design-basis RIA and LOCA in the MIR reactor | + | | {{ : |
| - | | Current and Prospective Tests in Reactor MIR | A.L. Izhutov | + | | {{ : |
| - | | INL TRANSIENT REACTOR RESTART PROGRESS | + | | {{ : |
| - | | Internal Peer Review (IPR) of Pakistan Research Reactor-I (PARR-I) | + | | {{ : |
| - | | Safety assessments of the Tehran research reactor | + | | {{ : |
| - | | SAFARI-1 SAFETY REASSESSMENT AND MODIFICATIONS IN LIGHT OF THE FUKUSHIMA DAICHI ACCIDENT | + | | {{ : |
| - | | WWR-K Reactor Safety Reassessment | + | | {{ : |
| - | | Safety Reassessments and Actions Taken in HANARO since Fukushima | + | | {{ : |
| - | | Safety Reassessment of Research Reactors in the Light of the Lessons Learned from the Fukushima-PAA point of view. Selected Issues. | + | | {{ : |
| - | | New Safety Requirements Addressing Feedback From the Fukushima Daiichi Accident | + | | {{ : |
| - | | Experience with Safety Reviews of Slovenian Research Reactor by PSR and IAEA INSARR Missions and the Stress Tests for the Krško NPP | + | | {{ : |
| - | | SAFARI-1 SAFETY REASSESSMENT AND MODIFICATIONS IN LIGHT OF THE FUKUSHIMA DAICHI ACCIDENT | + | | {{ : |
| - | | Thermal Hydraulic Analysis of 49-2 Swimming Pool Reactor with a Passive Siphon Breaker | + | | {{ : |
| - | | Modifications on TR-2 Reactor Against an Expected Earthquake | + | | {{ : |
| - | | Assessment of Lessons Learned from the Fukushima Dai-ichi Nuclear Accident to Research and Test Reactors in the United States | + | | {{ : |
| - | | Introduction of Nation-wide Inspection and Reassessment to Chinese Research Reactors after Fukushima Accident | + | | {{ : |
| - | | Safety reassessment of Egyptian second research reactor post Fukushima accident | + | | {{ : |
| - | | Regulatory requirements to carry out Complementary Safety Assessments and to implement Hardened Safety Core provisions in the Light of the Lessons Learned from the Fukushima Daiichi Accident | + | | {{ : |
| - | | Safety Reassessment of German Research Reactors in the Light of the Accident at the Fukushima Daiichi Nuclear Power Plant | + | | {{ : |
| - | | Considering Fukushima lessons for the Budapest Research Reactor | + | | {{ : |
| - | | Safety Enhancement of Dhruva Reactor through Periodic Safety Review | + | | {{ : |
| - | | Safety Reevaluation of Indonesian MTR-Type Research Reactor | + | | {{ : |
| + | | {{ : | ||
| + | </ | ||
proceedings/2017_igorr18.1703847377.txt.gz · Last modified: 2023/12/29 11:56 by Joerg Pulz