Past events – Nuclear power reactors

Year

Type

Topics

7 – 10 May 2018

Vienna, Austria

Event Code: EVT1703134

Second Research Coordination Meeting on Design and Performance Assessment of Passive Engineered Safety Features in Advanced Small Modular Reactors

23 – 26 Apr 2018

Vienna, Austria

Event Code: EVT1701654

First Meeting of the Technical Working Group on Small or Modular Reactors

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

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Past events – Nuclear power reactors

Second Research Coordination Meeting on Design and Performance Assessment of Passive Engineered Safety Features in Advanced Small Modular Reactors

First Meeting of the Technical Working Group on Small or Modular Reactors

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

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Past events – Nuclear power reactors

More Meetings

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