The first QUENCH-ATF joint project test was successfully completed by the KIT team on 17 July 2022.
Published date:
5 August 2022
High-temperature gas-cooled nuclear reactors are one of the next generation reactor designs. This benchmark consists consists in a multi-staged code-to-code-to-data thermal hydraulics code validation...
Published date:
8 August 2022
The quality of the isotopic composition of plutonium fuel degrades as the number of recycles increases in thermal reactors. There are in addition incentives to better utilise fuel by increasing the b...
Published date:
19 July 1995
The Shielding Integral Benchmark Archive and Database (SINBAD) database contains compilations for 46 reactor shielding, 31 fusion neutronics and 23 accelerator shielding experiments.
Published date:
4 August 2022
The primary purpose of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) is to compile critical and subcritical benchmark experiment data into a standardised format that allo...
Published date:
4 August 2022
An approach similar to the OECD/NRC Boiling Water Reactor Full-size Fine-mesh Bundle Tests (BFBT) Benchmark was adopted by dividing the benchmark activity into phases.
Published date:
2 August 2022
This benchmark incorporated full 3-D modelling of the reactor core into system transient codes for best-estimate simulations of the interactions between reactor core behaviour and plant dynamics and ...
Published date:
2 August 2022
Forsmark 1 and 2 Boiling Water Reactor Stability Benchmark
Published date:
2 August 2022
NUPEC Boiling Water Reactor (BWR) Full-size Fine-mesh Bundle Test (BFBT) Benchmark
Published date:
2 August 2022
A number of tests with detail well documented neutronics and thermal-hydraulics measurements data have been performed at the Rostov Unit 2 (Rostov-2) nuclear power plant (NPP). The reactor type is a ...
Published date:
2 August 2022
22 -
26 May 2023
Bologna, Italy
Published date:
2 August 2022
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...
Published date:
2 August 2022
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 ...
Published date:
2 August 2022
The overall objective of the VVER-1000 Coolant Transient (V1000CT) Benchmark was to assess computer codes used in the safety analysis of water-water energetic reactor (VVER) power plants, specificall...
Published date:
2 August 2022
The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, and radiation transport and shielding in present and future nu...
Published date:
2 August 2022
Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS), the Expert Group on Physics of Reactor Systems (EGPRS) performs specific tasks associa...
Published date:
2 August 2022
The Expert Group on Reactor Systems Multi-Physics (EGMUP) advances the state of the art in establishing processes and procedures for certifying experimental data and benchmarking multi-physics multi-...
Published date:
2 August 2022
Created in 2019, under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS) the expert group will perform specific tasks associated with core thermal-hydraulics aspects of...
Published date:
2 August 2022
Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) the expert group performs specific tasks associated with fuel performance aspects of pr...
Published date:
2 August 2022
The NEA Data Bank organised a PENELOPE training course at the University of Barcelona in Spain on 11-15 July 2022
Published date:
1 August 2022
Over its 25 years of existence, the working party has contributed many topics and has led advances in criticality safety studies.
Published date:
28 July 2022
The NEA Data Bank's first in-person course since the pandemic started was on FISPACT, an enhanced multi-physics platform for neutron, proton, alpha, deuteron or gamma particle interactions.
Published date:
27 June 2022
PWR MOX/UO2 Core Transient Benchmark
Published date:
19 July 2022
TVA Watts Bar Unit 1 Multi-Physics Benchmark
Published date:
19 July 2022
The Liquid Metal Fast Reactor (LFMR) is one of the next generation reactor designs. This benchmark consists of steady-state numerical predictions of Texas A&M University (TAMU) separate effect tests ...
Published date:
19 July 2022
Multi-physics Pellet Cladding Mechanical Interaction Validation (MPCMIV) Benchmark
Published date:
19 July 2022
Building on the NEA BFBT and PSBT benchmarks, McMaster University, in collaboration with North Carolina State University, launched a CANDU thermal-hydraulic benchmark under the WPRS Expert Group on U...
Published date:
19 July 2022
To ensure reliable modelling of neutron physics within a state-of-the-art transient code, the neutron kinetics part of such a code should be based on the full-scale calculation of the space-time neu...
Published date:
19 July 2022
This benchmark was a continuation of the V1000CT activities and defined a coupled code problem for further validation of thermal-hydraulics system codes for application with Russian-designed VVER-100...
Published date:
19 July 2022
The Boiling Water Reactor Turbine Trip (BWRTT) Benchmark was established to challenge the coupled system thermal-hydraulic/neutron kinetics codes against a Peach-Bottom-2 (a GE-designed BWR/4) turbin...
Published date:
19 July 2022
30 May 2022 -
3 June 2022
Conference Center Hotel Aquabella, Aix-en-Provence, France (in-person meeting)
Published date:
29 March 2022
The goal of the Benchmark for Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of Light Water Reactors (LWR-UAM) is to determine the uncertainty in light wate...
Published date:
5 July 2022
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 ...
Published date:
1 July 2022
The brochure provides background information about the NEA.
Published date:
10 September 2018
The NEA Framework for Irradiation Experiments (FIDES) supports the fuel and material experimental needs of nuclear safety regulators, technical support organisations, research institutions and indust...
Published date:
28 June 2022
This benchmark is organised to examine the models for fission gas release during anticipated operational occurrences (AOOs).
Published date:
30 June 2022
The Global Forum on Nuclear Education, Science, Technology and Policy acts as an inclusive network of experts in the nuclear energy sector, primarily from academia, focused on enabling the generation...
Published date:
26 May 2021
Recent meetings of groups working under the aegis of the Framework for Irradiation Experiments (FIDES) have demonstrated that the international community is enthusiastic and on a strong course to ful...
Published date:
5 May 2022
DATIF, the DATabase for IFpe, was first developed in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the NE...
Published date:
23 July 2020
The FIDES framework is designed to do more than just produce data on transient fuel behavior and safety related issues.
Published date:
28 June 2022
High-temperature gas-cooled reactors (HTGRs), also known as very-high-temperature reactors (VHTR) are Generation IV reactors that can operate at very high temperatures and use a graphite-moderated ga...
Published date:
22 June 2022
WPRS gathered 172 experts from 22 countries at the annual Benchmark Workshop.
Published date:
9 June 2022
Burn-up credit is a safety approach that accounts for the reduction in the reactivity of configurations with spent nuclear fuel due to the change in their composition after irradiation.
Published date:
2 June 2022
27 June 2022 -
1 July 2022
OECD headquarters, Paris XVI
Published date:
1 June 2022
The NEA Data Bank Nuclear Data Service (NDS) organised the Joint Evaluated Fission and Fusion (JEFF) Nuclear Data Week (NDW) on 25-29 April 2022.
Published date:
20 May 2022
The Working Party on Nuclear Criticality Safety (WPNCS) deals with technical and scientific issues relevant to criticality safety. Specific areas of interest include (but are not limited to) investig...
Published date:
17 May 2022
Nuclear Data Sensitivity Tool (NDaST), aims to provide rapid feedback on the effect of changes to nuclear data on integral benchmarks.
Published date:
17 May 2022
Accident-tolerant fuels may offer opportunities to enhance the safety and competitiveness of commercial nuclear power plants.
Published date:
16 December 2019
The International Criticality Safety Benchmark Evaluation Project (ICSBEP) released the first version of the Database for the International Handbook of Evaluated Criticality Safety Benchmark Experime...
Published date:
25 April 2022
Collected sources of primary documentation for reactor physics benchmarks.
Published date:
14 April 2022
English