Past events – Division of Nuclear Power

Type

Topics

27 – 29 Mar 2018

Vienna, Austria

Event Code: EVT1700250

Seventh Joint IAEA–GIF Technical Meeting/Workshop on the Safety of Liquid Metal Cooled Fast Reactors

26 – 27 Mar 2018

Vienna, Austria

Event Code: EVT 1704693

Twelveth GIF-IAEA Interface Meeting

26 – 29 Mar 2018

Vienna, Austria

Event Code: EVT1703131

First Research Coordination Meeting on Development of Approaches, Methodologies and Criteria for Determining the Technical Basis for Emergency Planning Zone for Small Modular Reactor Deployment

20 – 22 Mar 2018

Vienna, Austria

Event Code: EVT1703129

First Research Coordination Meeting on a Methodology for Assessing Pipe Failure Rates in Advanced Water Cooled Reactors

20 – 22 Mar 2018

Vienna, Austria

Event Code: EVT1703128

First Research Coordination Meeting on a Probabilistic Safety Analysis Benchmark for Multi-Unit, Multi-Reactor Sites

12 – 14 Mar 2018

Vienna, Austria

Event Code: EVT1700244

Technical Meeting on Research and Technology Needs to Enable Increased Operating and Accident Temperatures for High Temperature Reactors

27 Feb – 2 Mar 2018

Vienna, Austria

Event Code: EVT1703149

Fifth Research Coordination Meeting on Sodium Properties and Safe Operation of Experimental Facilities in Support of the Development and Deployment of Sodium Cooled Fast Reactors

19 – 23 Feb 2018

Sharjah, United Arab Emirates

Event Code: EVT1703123

Regional Training Course on Pressurized Water Reactor Technology Using PC Based Basic Principle and GlassTop Nuclear Power Plant Simulators

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Past events – Division of Nuclear Power

Seventh Joint IAEA–GIF Technical Meeting/Workshop on the Safety of Liquid Metal Cooled Fast Reactors

Twelveth GIF-IAEA Interface Meeting

First Research Coordination Meeting on Development of Approaches, Methodologies and Criteria for Determining the Technical Basis for Emergency Planning Zone for Small Modular Reactor Deployment

First Research Coordination Meeting on a Methodology for Assessing Pipe Failure Rates in Advanced Water Cooled Reactors

First Research Coordination Meeting on a Probabilistic Safety Analysis Benchmark for Multi-Unit, Multi-Reactor Sites

Technical Meeting on Research and Technology Needs to Enable Increased Operating and Accident Temperatures for High Temperature Reactors

Fifth Research Coordination Meeting on Sodium Properties and Safe Operation of Experimental Facilities in Support of the Development and Deployment of Sodium Cooled Fast Reactors

Regional Training Course on Pressurized Water Reactor Technology Using PC Based Basic Principle and GlassTop Nuclear Power Plant Simulators

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Past events – Division of Nuclear Power

More Meetings

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Stay in touch

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