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Publications and Reports
International Evaluation Co-operation, Volume 7

Subgroup 7 of the NEA Working Party on International Nuclear Data Co-operation (WPEC) was established to re-evaluate the nuclear data standards cross-section. These cross-section data are the basis f...

English WPEC NSC Nuclear science Nuclear data Nuclear science …
Published date: 29 November 2006
Publications and Reports
Source Convergence in Criticality Safety Analyses - Phase I: Results for Four Test Problems

The NEA Working Party on Nuclear Criticality Safety (WPNCS) established an Expert Group on Source Convergence in Criticality Safety Analysis (EGSCCSA) to explore the problems of slow convergence and ...

English Nuclear science Nuclear science
Published date: 11 September 2006
Publications and Reports
Very High Burn-ups in Light Water Reactors

Average fuel burn-up in light water reactors (LWRs) has steadily increased with time as technological advances have been made. The practical limit is currently in the region of 50 GWd/t. The main dri...

English Nuclear fuel Reactor physics Fuel studies Nuclear science Light water reactors Nuclear science Reactor physics …
Published date: 22 August 2006
Publications and Reports
Nuclear Production of Hydrogen

Hydrogen has the potential to play an important role as a sustainable and environmentally acceptable energy carrier in the 21st century. Since natural sources of pure hydrogen are extremely limited, ...

English Nuclear science Hydrogen Nuclear science
Published date: 13 July 2006
Publications and Reports
English Nuclear science Nuclear science
Published date: 7 July 2006
Publications and Reports
NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) Benchmark

Refined models for best-estimate calculations based on good-quality experimental data can improve the understanding of phenomena and the quantification of margins for operating nuclear power reactors...

English Reactor physics Nuclear science Multiphysics Nuclear science Benchmark Reactor physics Multiphysics …
Published date: 7 July 2006
Publications and Reports
French Nuclear science Nuclear science
Published date: 19 May 2006
Publications and Reports
English Nuclear science 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 Nuclear science
Published date: 11 April 2006
Publications and Reports
English Nuclear science Nuclear science
Published date: 7 February 2006