The next annual Benchmarks Workshops of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) will be hosted by the Department of Engineering of the University of ...

The NEA International Criticality Safety Benchmark Evaluation Project (ICSBEP), International Reactor Physics Experiments Evaluation Project (IRPhEP), International Assay Data of Spent Nuclear Fuel D...

The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) and its expert groups co-ordinate benchmark activities on Reactor Single- and Multi-Physics. The benchmark ac...

NEA released the International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook which contains criticality safety benchmark specifications

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at...

Under the auspices of the Nuclear Energy Agency (NEA) Nuclear Science Committee (NSC), the Working Party on Scientific Issues of Reactor Systems (WPRS) has been established to study reactor physics, ...

Participants from 14 organisations, representing 11 countries, performed the benchmark exercise. Each participant provided a high-level summary of the leak-before-break (LBB) requirements in their co...

The NEA Nuclear Science Committee (NSC) mandated the Expert Group on Multi-Physics Experimental Data, Benchmarks and Validation (EGMPEBV) in 2014 to provide oversight of activities associated with th...

The International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE) contains reactor physics benchmark specifications that have been derived from experiments that were performed at ...

WPRS organised annual benchmarks workshop.

At its 61st meeting, the CSNI approved the recommended task on the benchmark on external events hazard frequency and magnitude statistical modelling, to be pursued by the WGEV. Modelling of these ext...

The annual Benchmark Workshops of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) was co-located with the BEPU 2024 conference and hosted by N.IN.E. (Nuclear...

The Shielding Integral Benchmark Archive and Database (SINBAD) database contains compilations for 46 reactor shielding, 31 fusion neutronics and 23 accelerator shielding experiments.

Many of the failures that occur in nuclear fuel rods in light water reactors around the world are caused by the phenomenon of mechanical interaction between pellets and cladding (PCMI). The process i...

Many of the failures that occur in nuclear fuel rods in light water reactors around the world are caused by the phenomenon of mechanical interaction between pellets and cladding (PCMI). The process i...

The meetings took place in April 2024 in the United States.

This report provides the results of the fluid structure interaction (FSI) benchmark, which was developed and performed by the designer and engineering company OKBM as part of NEA and ROSATOM activiti...

The NEA International Criticality Safety Benchmark Evaluation Project (ICSBEP) and International Reactor Physics Experiments Evaluation Project (IRPhEP) Technical Review Groups, and the Shielding Int...

Under the guidance of the NEA Nuclear Science Committee (NSC), the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance,...

The benchmark will predict the Critical Heat Flux (CHF).

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...

The Task Force on Dose Rate Calculations for Irradiated Fuel Assembly was launched in 2015 to assess code predictions of dose rates from bare spent fuel assemblies and to benchmark multiple codes and...

The NEA Working Party on Nuclear Criticality Safety (WPNCS) held its bi-annual meetings in June 2023

High-temperature gas-cooled nuclear reactors are one of the next generation reactor designs. This benchmark consists of a multi-staged code-to-code-to-data thermal hydraulics code validation benchmar...

Kick-off workshop of the thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using High Temperature Test Facility (HTTF) data.

The annual WPRS Benchmarks Workshops took place on 22-26 May 2023 in Bologna, Italy.

Lead-cooled Fast Reactors (LFR) are rather new concepts which have gathered increasing international attention after the Generation-IV International Forum (GIF) selected them as promising candidates ...

The NEA thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using HTTF data (HTGR T/H), supervised by the Expert Group on Reactor Core Thermal-Hydraulics and Mechanic...

The annual Benchmark Workshops of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems will be hosted by the Italian National Agency for New Technologies, Energy and Sus...

The Technical Review Groups for both projects met at the NEA headquarters on 3-7 April 2023.

Since the early 2000s there is an increasing demand from nuclear research, industry, safety and regulation for best-estimate predictions to be provided with their confidence bounds. Consequently, an ...

This report presents the results of a benchmark study on innovative fuels for fast reactors using fuel performance codes. Irradiation results were shared among participants of the expert group and co...

The WPRS met from 20-24 February 2023.

This benchmark is organised to examine the models for fission gas release during anticipated operational occurrences (AOOs).

This benchmark report has been compiled under the guidance of the NEA Working Party on Nuclear Criticality Safety (WPNCS) in the Subgroup on the Role of Integral Experiment Uncertainties and Covarian...

The 2021 edition contains data from 169 experimental series that were performed at 57 nuclear facilities.

Please note that this report was initially published in November 2022 (NEA/NSC/R(2022)3) under erroneous benchmark number IIB; in this updated version (NEA/NSC/R(2022)3/CORR) this has been corrected ...

The 2021 edition can be downloaded online.

The modelling and simulation of nuclear systems allow scientists and engineers to probe aspects of the operation of these systems beyond what has been precisely measured. This has numerous applicatio...