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...

Heavy liquid metals such as lead or lead-bismuth have been proposed and investigated as coolants for fast reactors since the 1950s. More recently, there has been renewed interest worldwide in the use...

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...

Monte Carlo criticality calculations involve a two-step procedure based on a stochastic implementation of the power iteration method: first, achieve convergence of the fission source distribution dur...

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

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...

Since 2007, the NEA has organised a series of workshops on structural materials for innovative nuclear systems (SMINS). The fifth meeting, held from 8‑11 July 2019 in Kyoto, Japan, was hosted by Kyot...

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...