The present report summarises the main results and learnings from the third phase of the NEA Behaviour of Iodine Project (BIP-3), which was conducted between 2016 and 2019 by the Canadian Nuclear Lab...

In order to reach a better understanding of countries’ different approaches to the evaluation of vibrations detected in piping systems and components, the NEA Committee on the Safety of Nuclear Insta...

The aim of this report is to examine whether there are any international variations in the electrical power system designs (“design variations”) of nuclear power plants that affect the system respons...

In the ASCET Phase III, the goal was to assess and develop the Phase II (blind benchmark) recommendations using additional test results. The Phase III simulations were performed using a full set of t...

The NEA Working Group on Digital Instrumentation and Controls (WGDIC) has agreed that a consensus position on the impact of cyber security features on digital instrumentation and control (I&C) system...

This report presents a study performed on a set of common-cause failure (CCF) events within the International Common-cause Failure Data Exchange (ICDE) Project. The topic was multi-unit CCF events.

T...

This report presents a study performed on a set of common-cause failure (CCF) events within the Nuclear Energy Agency (NEA) International Common-cause Failure Data Exchange (ICDE) Project. The topic ...

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...

Since its inception in 2002, the operating experience with thermal fatigue mechanisms has been an intrinsic aspect of the technical scope of CODAP, which is a joint database project within the Commit...

This report summarises the work done for the activity: “Benchmark analysis on the eXtended Finite Element Method (X-FEM) calculation technology in its use to evaluate the fracture mechanics stress in...

The VeRCoRs facility mock-up is a reactor containment building at 1/3 scale. The mock-up is instrumented so that its behaviour is monitored from the beginning of construction. More than 700 sensors a...

CSNI and CNRA held their biannual meetings and a joint session at the NEA headquarters.

Independent safety regulation has been a hallmark of the global nuclear power sector from its beginnings. Industry and government have long understood the importance of a predictable and adaptable re...

The CNRA believes in the importance of having a working group dedicated to safety culture. The Working Group on Safety Culture (WGSC) provides a senior level regulatory forum for exchanging informati...

The NEA Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Installations (CSNI) held their biannual meetings from 6 to 9 December 2021 and discussed the evol...

This technical report describes the regulatory perspectives on safety aspects related to the fuel qualification for advanced sodium fast reactors (SFRs) and identifies topics that should be investiga...

CNRA/CSNI meetings, May-June 2021.