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The global objective of the SafeG project is to further develop the GFR technology and strengthen its safety. The project shall support the development of nuclear low-CO2 electricity and industrial process heat generation technology.


The objectives are to validate the laser cutting technology for the dismantling of the most challenging components of power nuclear reactors in air and underwater and demonstrate that the in-air and underwater laser cutting technologies are a relevant alternative to the conventional techniques used for the segmentation of the power nuclear reactors internals (RVI) and pressure vessels (RPV).


The overall aim of sCO2-4-NPP is to contribute to an increased safety of Nuclear Power Plants (NPPs) in case of accidents by further specifying, designing and validating the sCO2-based heat removal system developed in the previous sCO2-HeRo project on a NPP and preparing the necessary roadmaps to bring it closer to industrial use.


The project mainly aims at consolidating assessments of the radiological consequences (RC) of explicit DBA and DEC-A reactor accidental situations through updated calculation schemes and harmonized methodologies from which some rationales for EP&R action optimisation will be derived.


The PUMMA project will define different options for Pu management in Generation-IV systems and evaluate the impact on the whole fuel cycle in addition to safety and performance aspects.


OBJECTIVES High level objectives of the PREDIS project are: Develop solutions, methods, processes, technologies and demonstrators, for future treatment and conditioning of waste for which no or inadequate solutions are currently available, in order to avoid construction of new storage on sites, or improve existing solutions with safer, cheaper or more effective alternative processes with


The overall objective of PASTELS is to improve the ability of European nuclear actors to design and deliver innovative passive safety systems and simulate their behaviour to support the safety demonstration.


ORIENT NM seeks to explore the possibility and critically assess the added value of establishing a Co Funded European Partnership ( to support the development of a coordinated pan European research and innovation programme on nuclear materials positively impacting Europe’s competitiveness in the nuclear field at world scale.


NUCOBAM will develop the qualification process and provide the evaluation of the in-service behaviour allowing the use of additively manufactured (AM) components in a nuclear installation. Once qualified, the use of AM will allow nuclear industry to (1) tackle component obsolescence challenges and (2) manufacture and operate new components with optimised design in order to increase reactor efficiency and safety.


INNO4GRAPH aims to develop a set of physical and digital tools and methods to be used in two different phases of European graphite reactor dismantling projects: tools to be used during tests and studies upstream of the dismantling operations and tools to be used during the dismantling operations.


The goal of this project is to join European and international efforts to establish the foundation of small specimen fracture toughness validation and demonstration to achieve change in code and standards allowing to address the various national regulatory authority concerns.


The overarching objective of the European Database for Multiscale Modelling of Radiation Damage (ENTENTE) project is to capitalise on past projects and expert groups beyond national borders, to make modelling and experimental work on RPV steel embrittlement converge and reach an “entente” in terms of capturing the expansive knowledge on the relevant ageing phenomena.


The overall objective of BESEP is to support safety margins determination by developing best practices for safety requirements verification against external hazards, using efficient and integrated set of Safety Engineering practices and probabilistic safety assessment.


One of the most limiting safety assessments for long term operation (LTO) of nuclear power plants (NPP) is the reactor pressure vessel (RPV) integrity assessment for pressurized thermal shock (PTS). The goal is to demonstrate the safety margin against fast fracture initiation or RPV failure.


ACES will improve the understanding of ageing/deterioration of concrete, and will demonstrate and quantify inherent safety margins introduced by the conservative approaches used during design and defined by codes and standards employed throughout the life of the plant.