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Publications and Reports
Physics of Plutonium Recycling - Volume VIII

The NEA has studied multiple recycling issues associated with various reactor systems fuelled with mixed-oxide (MOX) and published a series of computational physics benchmarks. This has led to improv...

English Nuclear science Plutonium Liquid metal reactors Advanced reactors Reactor physics Recycling and reuse Reactor physics NSC Gas-cooled reactors Fuel cycle technology Fuel cycle physics and chemistry Pressurised water reactors …
Published date: 21 June 2007
Joint project
Plant Safety Monitoring and Assessment System (PLASMA) Project

Under an agreement with the Japan Atomic Energy Research Institute, (JAERI), the NEA supported an international research project with the goal of developing a plant safety monitoring and assessment s...

Risk assessment Accident analysis and management Nuclear safety research Joint project Accident management Pressurised water reactors Safety research …
Published date: 22 April 2020
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 Nuclear science Nuclear safety research Safety of components and structures Thermal hydraulics and mechanics Modelling and simulation Thermal hydraulics Verification and validation Uncertainty analysis Nuclear science Benchmark Pressurised water reactors …
Published date: 1 January 1999
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 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 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
Joint project
PSB-VVER Project

Scheme of the PSB-VVER facility, EREC

The NEA PSB-VVER project provided unique and useful experimental data for code validation using the PSB-VVER test facility. The PSB-VVER facility is a large-scal...

Accident analysis and management Thermal hydraulics Nuclear safety research Joint project Pressurised water reactors Safety research …
Published date: 6 October 2023
NEA Document
Solving Thermal Hydraulic Safety Issues for Current and New Pressurised Water Reactor Design Concepts: Primary Coolant Loop Test Facility (PKL2) Project – Final Report
NEA/CSNI/R(2017)6

For many years, extensive experimental investigations into the system response of pressurised water reactors (PWRs) under accident conditions have been being conducted at the large-scale Primärkreisl...

English Nuclear safety research CSNI Pressurised water reactors
Published date: 17 January 2018
NEA Document
English Risk assessment Fuel cycle facility safety Nuclear safety research CSNI Safety of components and structures Pressurised water reactors Risk Safety research …
Published date: 1 January 1998
NEA Document
The Effect of Temperature on the Neutron Multiplication Factor for Pressurised Water Reactor Fuel Assemblies: A Temperature Analysis Benchmark
NEA/NSC/R(2022)1

There is significant international interest in the effects of temperature on criticality safety evaluations. Improved access to nuclear data, notably thermal scattering data S(α,β) for hydrogen in ic...

Nuclear science WPNCS Benchmark Pressurised water reactors
Published date: 2 November 2023