research reactor | research-type nuclear reactor

multipurpose research reactor

high flux research reactor

Exposure to radiation from nuclear reactor because of reactor malfunction

nuclear reactor [ atomic power cell | boiling water reactor | fast neutron reactor | fusion reactor | gas-cooled reactor | light-water reactor | power reactor | pressurised water reactor | thermal reactor | thermonuclear reactor | water-moderated reactor | water reactor ]

Reduced Enrichment for Research and Test Reactors | RERTR [Abbr.]

Seminar on Applied Research and Service Activities for Research Reactor Operations

Exposure to radiation from nuclear reactor

Exposure to radiation from nuclear reactor because of meltdown

Agreement between the International Atomic Energy Agency and the Governments of Canada, Jamaica and the United States of America concerning the Transfer of Enriched Uranium for a Low Power Research Reactor

In line with the general objective, support to joint research activities concerning the safe operation and decommissioning of reactor systems (including fuel cycle facilities) in use in the Union or, to the extent necessary in order to maintain broad nuclear safety expertise in the Union, those reactor types which may be used in the future, focusing exclusively on safety aspects, including all aspects of the fuel cycle such as partitioning and transmutation.

In line with the general objective, support to joint research activities concerning the safe operation and decommissioning of reactor systems (including fuel cycle facilities) in use in the Union or, to the extent necessary in order to maintain broad nuclear safety expertise in the Union, those reactor types which may be used in the future, focusing exclusively on safety aspects, including all aspects of the fuel cycle such as partitioning and transmutation.

shipment of spent fuel of research reactors to a country where research reactor fuels are supplied or manufactured, taking into account applicable international agreements.

Research to underpin the continued safe operation of all relevant types of existing reactor systems (including fuel cycle facilities), taking into account new challenges such as life-time extension and development of new advanced safety assessment methodologies (both the technical and human element) including as regards severe accidents, and to assess the potential, the safety and waste-management aspects of future reactor systems, in the short and medium term, thereby maintaining the high safety standards already achieved within the EU and considerably improving the long-term management of radioactive waste.