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
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
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
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
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
The aim of the benchmark is to improve understanding and modelling of pellet-cladding mechanical interaction (PCMI) amongst NEA member organisations. This is achieved by comparing PCMI predictions of...
Published date:
23 March 2022
The IRPhEP Database and Analysis Tool (IDAT) was first released in 2013 and is included on the IRPhE Handbook DVD. This database and corresponding user interface allows easy access to handbook inform...
Published date:
17 March 2022
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...
Published date:
23 November 2021
The Expert Group on Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF) dealt with the various aspects of the modelling and design of accelerator shield systems and radiatio...
Published date:
19 November 2021
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...
Published date:
27 October 2021
Helium-cooled very high-temperature gas reactors are highlighted as a key technology with the potential to improve the competitiveness of nuclear energy within the Generation IV International Forum (...
Published date:
20 September 2021
For nuclear utility companies that opt to reprocess spent fuel, recycle it or do both, one of the main pertinent issues is plutonium recycling.
Published date:
8 September 2021
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...
Published date:
26 July 2021
The international benchmark concerned pebble bed modular reactor (PBMR) coupled neutronics/thermal-hydraulics transients based on the PBMR-400MW design.
Published date:
26 July 2021
Fluoride salt-cooled high-temperature reactors (FHRs), cooled with liquid (molten) salt, fueled with TRISO-based fuel are a potential molten salt reactor (MSR) design.
Published date:
14 June 2021
The Technical Review Group (TRG) for the International Assay Data of Spent Nuclear Fuel Database (SFCOMPO) lies under the direction of the Working Party on Nuclear Criticality Safety (WPNCS).
Published date:
13 April 2021
The expert group critically reviewed integral experiments for validating minor actinide (MA) nuclear data, recommended additional integral experiments needed for validating MA nuclear data and invest...
Published date:
5 March 2021
A sodium-cooled fast reactor (SFR) is a fast neutron reactor that uses molten sodium metal as a coolant. Sodium-cooled Fast Reactors (SFRs) are the most promising type of reactors to achieve Generati...
Published date:
4 February 2021
The Expert Group on Reactor-based Plutonium Disposition (TFRPD) dealt with the status and trends of reactor physics, fuel performance and fuel cycle issues related to the disposition of weapons-grade...
Published date:
16 December 2020
SFCOMPO 2.0 (Spent Fuel Isotopic Composition) is a relational database designed to facilitate the search and visualisation of experimental assay data of spent nuclear fuel.
Published date:
2 October 2020
MeshTal Viewer is a Java based software which can read mesh tallies output formats of several neutron transport codes and display them graphically.
Published date:
2 October 2020
IRPhE Handbook 2019 Edition - Contents
Published date:
30 September 2020
The Nuclear Science Committee (NSC), through its expert group, conducted a study on research and development (R&D) needs in nuclear science, held a workshop on R&D needs for current and future nuclea...
Published date:
30 September 2020
Historically, average discharge burn-ups in light water reactors (LWRs) have steadily increased with time as experience has accumulated and technological developments have progressed. The main benefi...
Published date:
30 September 2020
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...
Published date:
30 September 2020
The page describes the NEA's work on computing radiation dose and modelling of radiation-induced degradation of reactor components.
Published date:
30 September 2020
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.
Published date:
30 September 2020
International Conference on Nuclear Data for Science and Technology
Published date:
28 September 2020
Sensitivities Viewer is a Java based software which can read sensitivities files and plot sensitivities profiles.
Published date:
25 September 2020
International Workshop on Nuclear Data Evaluation for Reactor Applications (WONDER)
Published date:
23 September 2020
Criticality is the state of a nuclear reactor when there is a self-sustaining chain reaction of fissionable material. Criticality experiments are controlled tests using fissile materials, like pluton...
Published date:
24 March 2020
A criticality excursion (also referred to as a criticality accident) is the accidental production of a self-sustaining or divergent chain reaction of fissionable material.
Published date:
24 March 2020
Criticality is the state of a nuclear reactor when there is a self-sustaining chain reaction of fissionable material. Used or spent fuel criticality is associated with the scientific issues around as...
Published date:
24 March 2020
Criticality is the state of a nuclear reactor when there is a self-sustaining chain reaction of fissionable material. Criticality safety analysis relates to evaluation approaches in data and computat...
Published date:
24 March 2020
Published date:
10 March 2020
The Collaborative International Evaluated Library Organisation (CIELO) Pilot Project, working under the auspices of the WPEC Subgroup 40 (SG40), was established to generate complete evaluations for a...
Published date:
10 March 2020
Nuclear data thermal scattering
Published date:
9 March 2020
Nuclear data fission physics
Published date:
9 March 2020
Nuclear data applications, verification and validation
Published date:
9 March 2020
Nuclear data measurements
Published date:
9 March 2020
Nuclear data covariance and assimilation
Published date:
9 March 2020
NEA work in nuclear data formats
Published date:
9 March 2020
Published date:
9 March 2020