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

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 ...

^{Figure 1: Generation IV International Forum [gen-4.org]}

The Nuclear Energy Agency (NEA) and Natural Resources Canada (NRCan) organised an international workshop on the implementation of radioactive w...

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...

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...

The event gathered 129 participants from 75 international institutions.

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 ...

WPRS gathered 172 experts from 22 countries at the annual Benchmark Workshop.

Collected sources of primary documentation for reactor physics benchmarks.

Proceedings of the Fourteenth Workshop, 30 October-2 November 2018, Gyeongju, Korea.

In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for boiling water reactor (BWR) fuel bundles. This international benchmark, bas...

The purpose of this prismatic High Temperature Reactor (HTR) benchmark is to provide a solution set that can be used in future code benchmarking and to better understand the effects induced by the pr...

For nuclear utility companies that opt to reprocess spent fuel, recycle it or do both, one of the main pertinent issues is plutonium recycling.

This benchmark focuses on FHR reactors with plates and triso fuel. Several phases are planned, starting with neutronics on a simple fuel element simulation without burn-up, and gradually extending to...

In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for Boiling Water Reactor (BWR) fuel bundles. This international benchmark, bas...

NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 15-19 February 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...

NEA Working Party on Scientific Issues of Reactor Systems (WPRS) workshops, 7-15 December 2020.

Understanding fuel performance is a key condition for successful reactor operation. Scientific knowledge in this domain was conceived by experimental tests encoded into software routines to ensure ac...

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 quality of the isotopic composition of plutonium fuel degrades as the number of recycles increases in thermal reactors, requiring an increase in the total loading necessary in mixed plutonium-ura...

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...

NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 19-21 February 2020.

Questions relating to the space, time end energy distribution of neutrons and radiation in different media are the domain of reactor physics.

The high-temperature gas-cooled reactor (HTGR) is a Generation IV reactor concept that uses a graphitemoderated gas-cooled nuclear reactor with a once-through uranium fuel cycle. This design permits ...

In 2013, the Expert Group on Reactor Physics and Advanced Nuclear Systems (EGRPANS) published a report that investigated fuel depletion effects in a pressurised water reactor (PWR). This was entitled...

Sodium fast reactors offer the most promising type of reactors to achieve such Generation IV goals at a reasonable time scale given the experience accumulated over the years. However, it is recognise...

The need to refine models for best-estimate calculations based on good-quality experimental data has arisen for various nuclear applications. One of the most extensive and valuable databases availabl...