Nuclear Fuel Cycle and Materials Section

Nuclear Power Reactor Fuel Engineering

Technical meeting on modelling of water-cooled fuel including design basis and severe accidents
28 October – 1 November
Nuclear Power Institute of China,
Chengdu, China


Nuclear fuel plays an essential role in ensuring safety, competitiveness and public acceptance of nuclear power. Reliability of fuel depends on its proper design, manufacturing, and ability to withstand required operational conditions. In-reactor loads on the core materials are extremely high, that defines a need for detailed R&D works as a basis for prediction of in-pile fuel behaviour. The Fukushima Daiichi accident has especially demonstrated necessity for adequate analysis of all aspects of fuel performance to prevent a failure, and also to mitigate its consequences if an accident occurs.

In the past years the demands on fuel duties have increased, including transient regimes, higher burnup and longer fuel cycles. In order to satisfy these demands new national and international programmes have been lounged and advanced modelling codes have been developed. The main focus of this TM will be to share the experience and lessons learned within these programmes aiming at analysis of fuel behaviour in both normal and off-normal conditions. Also specific role of the IAEA in this area will be highlighted, including the results of the recently finished chain of three Coordinated Research Projects on improvement of computer codes used for fuel behaviour modelling (FUMEX). A round-table discussion on the needs and perspectives on fuel modelling in accidental conditions will help to define a scope and out-line a new planned CRP on fuel modelling in accident conditions (FUMAC).

This TM was recommended by the IAEA Technical Working Group on Fuel Performance and Technology (TWGFPT) to be held in Chengdu in collaboration with the Nuclear Power Institute of China (NPIC).


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