Understanding the accident at the Fukushima Daiichi Nuclear Power Plant is important for safe and timely decommissioning of the reactors. This objective, together with the development of better compu...
In December 2008, the Committee on the Safety of Nuclear Installations (CSNI) approved a proposal of the Working Group on Integrity and Ageing of Components and Structures (WGIAGE) to conduct a round...
The NEA Working Group on Fuel Safety (WGFS) is tasked with advancing understanding of fuel safety issues by assessing the technical basis for current safety criteria and their applicability to high b...
This Phase II exercise was the first benchmarking of severe accident codes promoted by NEA in almost 20 years. The objective of the exercise was to perform a code benchmark on a well-defined plant (s...
At the Committee on the Safety of Nuclear Installations (CSNI) meeting of June 2002, a proposal for a benchmark on thermal fatigue in fluid mixing areas based on the test performed by the Commissaria...
The Committee on the Safety of Nuclear Installations (CSNI) Workshop on Structural Reliability Evaluation and Mechanical Probabilistic Approaches of NPP Components was held in Lyon, France on 25-27 S...
The expert group dealt with the activities associated with the certification of experimental data and benchmark models along with establishing the processes and procedures for using the data and benc...
The expert group provided advice to the Working Party on Scientific Issues of Reactor Systems (WPRS) on the scientific development needs (data and methods, validation experiments, scenario studies) o...
Neutron noise analysis can be defined as the direct measurement of the kinetics of a nuclear core. This page describes some of the NEA's previous activities on neutron noise analysis in nuclear power...
3-D Radiation Transport benchmarks dealt with scientific issues in the field of deterministic and stochastic methods and computer codes relative to three dimensional (3-D) radiation transport.
Conditions for release, rules and restrictions applying to the Kalinin Unit 3 (Kalinin-3) Transient Benchmark caused by the switching-off of one of the four operating main circulation pumps (MCPs) at...
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...
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....
The Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of Light Water Reactors (LWRs) is an international high-visibility benchmark for unce...
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...
Under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS), the expert group performed specific tasks associated with radiation transport and shielding aspects of current ...
The page describes the NEA's work on computing radiation dose and modelling of radiation-induced degradation of reactor components.
WPEC Subgroup 47 (SG47) works in close coordination with other NEA activities such as WPRS Expert Group on Radiation Transport and Shielding (EGRTS), WPEC SG45, SG46, Collaborative International Eval...
Conditions for release, rules and restrictions applying to the specifications of the Fluoride Salt-Cooled High-Temperature Reactor (FHR) Benchmark
OECD Nuclear Energy Agency (NEA) and US Nuclear Regulatory Commission PWR MOX/UO2 Core Transient Benchmark Final Specifications, Revision 2 (2003)
NEA News is the professional journal of the Nuclear Energy Agency (NEA). It features articles on the latest nuclear energy issues concerning the economic and technical aspects of nuclear energy, nucl...