Authors & Affiliations

Belov A.A.1, Vasekin V.N.1, Veprev D.P.1, Veretentsev V.A.1, Veshchunov M.S.1, Mosunova N.A.1, Polous M.A.1, Stakhanova A.A.1, Strizhov V.F.1, Muratov A.G.2, Tukov V.V.2
1 Nuclear Safety Institute of the Russian Academy of Sciences, Moscow, Russian
2N.A. Dollezhal Research and Development Institute of Power Engineering, Moscow, Russian


EUCLID integrated code for safety analysis of nuclear reactors with sodium, lead-bismuth and lead coolants is being developed at the IBRAE of the Russian Academy of Sciences. EUCLID/VI version integrates several codes modeling core neutronics and thermal hydraulics transients for various fuel types. In 2013, cross-verification of EUCLID/VI code with DINAR dynamic code used for nuclear reactor projects justification was started. In the report, EUCLID/VI and DINAR codes are described, calculation results obtained by these codes being in a good agreement.

nuclear reactor, safety analysis, EUCLID integrated code, neutronics, thermal hydraulics, transients, DINAR code, cross-verification

Article Text (PDF)


UDC 621.039.58 : 004.94

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, issue 3:6, 2015