At the Nuclear Energy Agency (NEA), the importance of fuel modelling and its improvement through development of phenomenological representations has been recognised and multiple technical groups rela...

Experts met on 17-19 September for the 25^th WGFS annual meeting in Paris. 

This report established by the NEA Working Group on Fuel Safety (WGFS) of the Committee on the Safety of Nuclear Installations (CSNI) compiles the state-of-the-art knowledge on fuel behaviour in loss...

Rising international interest in increasing fuel burnup limits and fuel cycle length may require fuel enrichment above 5% and high reactivity/high suppression core designs. Based on this interest in ...

This document is intended to provide regulators, their technical support organisations and industry with a concise review of existing fuel experimental data at reactivity-initiated accident (RIA) and...

Experts from 16 countries met on 13-15 September for the 24^th annual Working Group on Fuel Safety GFS meeting in Paris. 

Two new reports from the WGFS highlight the latest developments in RIA research.

Following the recommendations from the technical workshop on “Nuclear Fuel Behaviour during Reactivity-Initiated Accidents” organised by the Nuclear Energy Agency (NEA) in September 2009, a first ben...

As a follow-up to the 2010 NEA report Nuclear Fuel Behaviour under Reactivity-initiated Accident (RIA) Conditions: State-of-the-art Report 2010, this report presents the state-of-the-art knowledge on...

Following the accident at the Fukushima Daiichi Nuclear Power Plant, many countries began funding research and development on nuclear fuel designs with enhanced accident tolerance (ATFs). ATFs have i...

One of the key areas in fuel safety is the analysis of fuel behaviour under reactivity-initiated accident conditions. Reactivity-initiated accident fuel rod codes have been developed for a significan...

This report documents the proceedings of the Workshop on Pellet-Cladding Interaction (PCI) in Water-Cooled Reactors held in Lucca, Italy on 22-24 June 2016. The workshop was organised jointly by the ...

Since the time of the first LOCA experiments, which were largely conducted with fresh fuel, changes in the fuel design, the introduction of new cladding materials and in particular the move to high b...

Reactivity-initiated accident (RIA) fuel rod codes have been developed for a significant period of time and validated against their own available database. However, the high complexity of the scenari...

Reactivity-initiated accident (RIA) fuel rod codes have been developed for a significant period of time and validated against their own available database. However, the high complexity of the scenari...

Spent fuel pools (SFPs) are large accident-hardened structures that are used to temporarily store irradiated nuclear fuel. Due to the robustness of the structures, SFP severe accidents have long been...

The impact of leaking fuel rods on the operation of nuclear power plants and the practices of handling leaking fuel has been reviewed by the CSNI Working Group on Fuel Safety (WGFS) in order to promo...