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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.

Funding Scheme

CSC - Cost-sharing contracts

Coordinator

UNIVERSITA DEGLI STUDI DI PISA
Address
Via Diotisalvi 2
56126 Pisa
Italy

Participants (6)

ASOCIACION NUCLEAR ASCO VANDELLOS
Spain
Address
Edifici Seu, L'hospitalet De L'infant
43890 Cala Doques
NUCLEAR RESEARCH INSTITUTE REZ A.S.
Czechia
Address

250 68 Rez - Praha
STUDSVIK ECO & SAFETY AB
Sweden
Address

611 82 Nykoping
SWEDISH NUCLEAR POWER INSPECTORATE
Sweden
Address

106 58 Stockholm
UNIVERSIDAD POLITECNICA DE MADRID
Spain
Address
C/josé Gutiérrez Abascal 2
28006 Madrid
UNIVERSIDAD POLITECNICA DE VALENCIA
Spain
Address
14,Camino De Vera S/n
46022 Valencia