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Validation of coupled neutronics/thermal hydraulics codes for VVER reactors

Validation of coupled neutronics/thermal hydraulics codes for VVER reactors

Objective

The proposal is aimed at the improvement of the validation of coupled neutronics / thermal hydraulic codes. Modern safety standards require a modelling of complex accident processes with significant interaction between thermal hydraulic system behaviour and space-dependent reactor kinetics. To perform the analysis of such events, thermal hydraulic system codes have to be coupled to three-dimensional core models. These coupled codes need to be validated against well-specified transient scenarios. The proposed work includes an extended validation of couple d codes against measurement data from NPPs, the development and application of an uncertainty analysis methodology for coupled codes and the validation of neutron kinetics models and nuclear cross section data libraries against kinetics.

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Coordinator

RESEARCH CENTER ROSSENDORF

Address

Germany

Administrative Contact

Frank POBELL

Participants (8)

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GESELLSCHAFT FUER ANLAGEN- UND REAKTORSICHERHEIT (GRS) MBH

Germany

INSTITUTE OF NUCLEAR RESEARCH AND NUCLEAR ENERGY - BULGARIAN ACADEMY OF SCIENCES

Bulgaria

KFKI RESEARCH INSTITUTE FOR MATERIALS SCIENCE

Hungary

NUCLEAR RESEARCH INSTITUTE REZ A.S.

Czechia

RUSSIAN RESEARCH CENTRE 'KURCHATOV INSTITUTE '

Russia

SLOVENSKE ELEKTRARNE, A.S.

Slovakia

STATE SCIENTIFIC AND TECHNICAL CENTRE ON NUCLEAR AND RADIATION SAFETY

Ukraine

VUJE TRNAVA INC - ENGINEERING, DESIGN AND RESEARCH ORGANISATION

Slovakia

Project information

Grant agreement ID: FIKS-CT-2001-00166

  • Start date

    1 January 2002

  • End date

    30 June 2004

Funded under:

FP5-EAECTP C

  • Overall budget:

    € 1 043 331

  • EU contribution

    € 672 902

Coordinated by:

RESEARCH CENTER ROSSENDORF

Germany