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NEA Document
Proceedings of the ICDE Workshop on the Qualitative and Quantitative Use of ICDE Data, Stockholm, Sweden, 12-13 June 2001
NEA/CSNI/R(2001)8
English Accident analysis and management Safety of electrical systems Nuclear safety research Ancillary data CSNI Joint project Safety Safety of components and structures Proceedings Safety research Risk assessment …
Published date: 10 April 2001
Joint project
Cable Ageing Data and Knowledge (CADAK) Project

In 2006, two subjects, stress corrosion cracking and the degradation of cable insulation were selected as the focus of the Stress Corrosion Cracking and Cable Ageing Project (SCAP). The project ran f...

Nuclear safety research Joint project Safety of components and structures
Published date: 17 April 2020
Joint project
Loss of Forced Coolant (LOFC) Project

The Committee on the Safety of Nuclear Installations (CSNI) Task Group on Advanced Reactor Experimental Facilities (TAREF) was established in 2007 and issued a report on the experimental facilities f...

Fuel in nuclear safety Experiments Accident analysis and management Nuclear safety research CSNI Safety Safety of components and structures Codes and programs Safety research Risk assessment Gas-cooled reactors Thermal hydraulics …
Published date: 7 April 2020
Joint project
Behaviour of Iodine Project (BIP)

The NEA Behaviour of Iodine Project (BIP) was created to provide separate effects and modelling studies of iodine behaviour in a nuclear reactor containment building following a severe accident. This...

Fuel in nuclear safety Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety Safety of components and structures Accident management Safety research …
Published date: 2 April 2020
Joint project
OECD-IAEA Paks Fuel Project

During a fuel crud removal operation on the Paks-2 unit on 10 April 2003, several fuel assemblies were severely damaged. The assemblies were being cleaned in a special tank of the Paks Nuclear Power ...

Fuel in nuclear safety Risk assessment Accident analysis and management Fuel cycle facility safety Nuclear safety research Safety of components and structures …
Published date: 20 April 2020
Joint project
Steam Explosion Resolution for Nuclear Applications (SERENA) Project

The Committee on the Safety of Nuclear Installations (CSNI) Working Group on Analysis and Management of Accidents (WGAMA) initiated a co-ordinated programme on Steam Explosion Resolution for Nuclear ...

Risk assessment Accident analysis and management Information, data and knowledge management Nuclear safety research Ancillary data Safety of components and structures …
Published date: 20 April 2020
Joint project
RASPLAV Project

The RASPLAV* Project was regarded as a successor to the Three Mile Island Vessel Investigation Project (TMI-VIP) completed in 1993. The TMI-VIP Project was set up to examine and assess the conditio...

Risk assessment Accident analysis and management Nuclear safety research CSNI Joint project Safety of components and structures …
Published date: 22 April 2020
Joint project
Melt Coolability and Concrete Interaction (MCCI) Project

In a core melt accident, if the molten core is not retained in-vessel despite severe accident mitigation actions, the core debris will relocate to the reactor cavity region and interact with the stru...

Risk assessment Light water reactors Accident analysis and management Fuel cycle facility safety Nuclear safety research Joint project Safety of components and structures Safety research …
Published date: 22 April 2020
Joint project
Material Scaling (MASCA) Project

The Material Scaling (MASCA) Project was a follow-up of the RASPLAV Project and investigated in-vessel phenomena during a severe accident. Specifically, it addressed the influence of the chemical c...

Risk assessment Accident analysis and management Nuclear safety research Joint project Safety of components and structures …
Published date: 22 April 2020
Joint project
Rod Bundle Heat transfer (RBHT) Project

The goal of the Rod Bundle Heat transfer (RBHT) Project is to conduct experiments in the RBHT facility in the United States in order to:

  • simulate reflood scenarios in a prototypical PWR rod bundle s...
Fuel in nuclear safety Risk assessment Accident analysis and management Thermal hydraulics Nuclear safety research CSNI Safety Safety of components and structures Safety research …
Published date: 8 April 2020