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Publications and Reports
VVER-1000 Coolant Transient Benchmark - Phase 1 (Vol. 2)

In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and co...

English Reactor physics Nuclear science Multiphysics Benchmark Reactor physics Pressurised water reactors Multiphysics …
Published date: 30 June 2006
Publications and Reports
English Nuclear science Proceedings
Published date: 26 June 2006
Publications and Reports
French Nuclear science
Published date: 19 May 2006
Publications and Reports
English Nuclear science
Published date: 18 April 2006
Publications and Reports
VENUS-2 MOX-fuelled Reactor Dosimetry Calculations

It is essential to calculate the structural integrity of reactor components with a high degree of accuracy in order to make correct decisions regarding plant lifetime at the design stage, safety marg...

English Nuclear science
Published date: 11 April 2006
Publications and Reports
English Nuclear science
Published date: 7 February 2006
Publications and Reports
VVER-1000 MOX Core Computational Benchmark

The United States and the Russian Federation have each agreed to dispose of 34 tonnes of weapons-grade plutonium that are beyond their defence needs. One effective way to dispose of this plutonium is...

English Modelling and simulation Reactor physics Nuclear science Benchmark Pressurised water reactors …
Published date: 20 January 2006
Publications and Reports
International Evaluation Co-operation, Volume 19

Neutron Activation Cross-section Measurements from Threshold to 20 MeV for the Validation of Nuclear Models and Their Parameters (Volume 19)

English WPEC NSC Nuclear science Nuclear data …
Published date: 12 December 2005
Publications and Reports
English Nuclear science Proceedings
Published date: 26 October 2005
Publications and Reports
Benchmark on Deterministic Transport Calculations Without Spatial Homogenisation

An important issue regarding deterministic transport methods for whole core calculations is that homogenised techniques can introduce errors into results. In addition, with modern computational abili...

English Nuclear science
Published date: 16 September 2005