The 15th workshop on Shielding aspects of Accelerators, Targets, and Irradiation Facilities (SATIF) is tentatively planned to be held in East Lansing, Michigan, USA, on 20-23 September 2022. The SATI...
NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 15-19 February 2021.
NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 19-21 February 2020.
As growing demand for energy has prompted ever-increasing use of fossil fuels, the resulting issues of energy security and climate change have in turn led to renewed interest in the use of hydrogen a...
The Shielding Integral Benchmark Archive and Database (SINBAD) database contains compilations for 46 reactor shielding, 31 fusion neutronics and 23 accelerator shielding experiments.
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...
The Subgroup on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM) was formed to check the use of best-estimate codes and data....
The EGMUP Task Force on artificial intelligence and machine learning will design benchmark specifications to evaluate the performance of AI/ML in multi-physics modeling and simulation of reactor syst...
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...
Thermal hydraulics and mechanics deals with the physics and mechanics of the flow and energetic transfer of liquids, and its interactions with the structures around them in large complex systems, suc...
The NEA Nuclear Science Committee (NSC) had organised two previous information exchange meetings on the nuclear production of hydrogen. The last of these meetings was held in October 2003, where deve...
Third Information Exchange Meeting on the Nuclear Production of Hydrogen including Second HTTR Workshop, Japan Atomic Energy Agency (JAEA), Oarai, Japan, 5 - 7 October 2005 - Programme
In this benchmark exercise the goal is to test the current state-of-the-art two-dimensional methods of calculating neutron flux to reactor components against the measured data of the VENUS-1 critical...
Average fuel burn-up in light water reactors (LWRs) has steadily increased with time as technological advances have been made. The practical limit is currently in the region of 50 GWd/t. The main dri...
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...
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...
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...
The annual Benchmark Workshop of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems was hosted by CEA Cadarache in Aix-en-Provence. During the week of 30 May to 3 June...
The annual Benchmark Workshop of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems will be hosted in 2023 by the Italian National Agency for New Technologies, Energy ...
