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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 Benchmark Reactor physics Multiphysics …
Published date: 7 July 2006
Publications and Reports
NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) Benchmark - Volume II

This report provides the specification for the uncertainty exercises of the international OECD/NEA, NRC and NUPEC BFBT benchmark problem including the elemental task. The specification was prepared j...

English Modelling and simulation Reactor physics Light water reactors Verification and validation Validation Uncertainty analysis Benchmark Reactor physics …
Published date: 1 January 2010
Publications and Reports
Benchmark on Deterministic Transport Calculations Without Spatial Homogenisation

One of the important issues regarding deterministic transport methods for whole core calculations is that homogenised techniques can introduce errors into results. On the other hand, with modern comp...

English Nuclear science
Published date: 8 August 2003
Publications and Reports
Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark - Volume III

This benchmark is based on a well-defined problem concerning a pressurised water reactor (PWR) main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the...

English Modelling and simulation Nuclear science Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics Pressurised water reactors …
Published date: 22 November 2002
Publications and Reports
Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark - Volume II

The benchmark is based on a well-defined problem concerning a PWR main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the main steam isolation valves....

English Modelling and simulation Nuclear science Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics Pressurised water reactors …
Published date: 22 December 2000
Publications and Reports
Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark - Volume I

Since the beginning of benchmark activities, two benchmark workshops took place. The first was held in Madrid, Spain (June 1998), and the second in Garching near Munich, Germany (March 1999). It was ...

English Modelling and simulation Nuclear science Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics Pressurised water reactors …
Published date: 1 January 1999
Publications and Reports
Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark - Volume IV

This benchmark is based on a well-defined problem concerning a pressurised water reactor (PWR) main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the...

English Modelling and simulation Nuclear science Thermal hydraulics Verification and validation Nuclear safety research Uncertainty analysis Safety of components and structures Benchmark Thermal hydraulics and mechanics Pressurised water reactors …
Published date: 19 November 2003
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
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 Reactor physics …
Published date: 22 August 2006
Publications and Reports
Minor Actinide Burning in Thermal Reactors

This publication provides an introduction to minor actinide nuclear properties and discusses some of the arguments in favour of minor actinide recycling, as well as the potential role of thermal reac...

English Fuel studies Nuclear science Reactor physics Fuel cycle physics and chemistry Minor actinides …
Published date: 18 November 2013
Publications and Reports
Reactor Noise - SMORN II
English Reactor physics Nuclear science Proceedings
Published date: 1 January 1977
Publications and Reports
Reactor Noise - SMORN I
English Reactor physics Nuclear science Proceedings
Published date: 1 January 1974
Publications and Reports
VVER-1000 Coolant Transient Benchmark - Phase 1 (Vol. 1)

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 …
Published date: 31 December 2003
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
VVER-1000 Coolant Transient Benchmark - Phase 1 (Vol. 3)

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 Nuclear science
Published date: 16 November 2007
Publications and Reports
VVER-1000 Coolant Transient Benchmark - Phase 2 (Ex. 1)

Recently developed best-estimate computer code systems for modelling 3-D coupled neutronics/thermal-hydraulics transients in nuclear reactors need to be validated against results from experiments and...

English Nuclear science
Published date: 5 October 2010
Publications and Reports
Basic Studies in the Field of High-temperature Engineering

In response to increasing interest in high-temperature, gas-cooled reactors (HTGRs) and the need for improved knowledge of materials for nuclear applications that resist high temperatures, the NEA or...

English Generation IV reactors Nuclear science Gas-cooled reactors Multiphysics Proceedings Reactor physics …
Published date: 1 January 2000
Publications and Reports
Basic Studies in the Field of High-temperature Engineering

In response to increasing interest in high-temperature, gas-cooled reactors (HTGRs) in many countries and the need for improved materials for nuclear applications in high-temperature environments, th...

English Generation IV reactors Nuclear science Gas-cooled reactors Multiphysics Proceedings Reactor physics …
Published date: 29 May 2002
Publications and Reports
Basic Studies in the Field of High-temperature Engineering

In response to growing interest in high-temperature, gas-cooled reactors (HTGRs) in many countries and the need for improved materials for nuclear applications in high-temperature environments, the N...

English Generation IV reactors Nuclear science Gas-cooled reactors Multiphysics Proceedings Reactor physics …
Published date: 1 June 2004
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