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Revisiting critical issues in nuclear reactor design / safety by using 3-d neutronics / thermalhydraulics models: state-of-the-art

Objective

The evaluation of NPP performance in case of RIA, is concerned. The activity exploits computer, computational tools and knowledge recently acquired. Western and Eastern NPP are concerned. 3-D neutron kinetics codes are coupled with system thermal hydraulic codes to calculate complex scenarios in relation to which, either no evaluation is available or overly conservative NPP design and operation margins are adopted. The activity is of benefit for reducing NPP costs even in relation to new reactors, for quantifying the actual NPP safety, for optimising the use of nuclear fuel including Plutonium, for making more transparent and generally for advancing the nuclear technology. Transients that may cause core power excursions originated by sudden increases of moderator density are directly considered. Emphasis is given to the qualification processes needed to obtain data. Industry, regulators and research organisations are involved.

Call for proposal

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Coordinator

UNIVERSITA DEGLI STUDI DI PISA
EU contribution
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Address
Via Diotisalvi 2
56126 PISA
Italy

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Total cost
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Participants (6)