Joint NEA-IAEA meeting on electrical power systems, 2‑5 December 2019
Advanced instrumentation for nuclear reactor thermal hydraulics experiments
NEA Committee on the Safety of Nuclear Installations (CSNI) meeting, 4‑5 December 2019.
The workshop was hosted by the French Institute for Radiological Protection and Nuclear Safety (IRSN) and the Nuclear Energy Agency (NEA)
The Nuclear Energy Agency (NEA) Commit...
In some countries, there is a growing demand for information about NPP performance from the executives, public and media. Such a demand has to be responded to and the information provided need to be ...
An International Workshop on Steam Generator Tube Integrity in Nuclear Power Plants, sponsored by the Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Inst...
Appendix C
The non-radiological risks involving dangerous chemicals in nuclear fuel cycle facilities,French framework regulation -
Accidents involving hazardous chemicals pose a significant threat to...
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 ...
NEA Working Group on External Events (WGEV) meeting, 14-18 September 2020.
The facilities associated with nuclear fuel from mining to fabrication to post-irradiation management have some specific safety concerns that are different from those of nuclear reactors.
The fuel for a nuclear reactor is both the source of the fission energy that is used to produce electricity and the source of radioactive material during an accident.
Risk assessments are used to determine the probability of harmful events at a nuclear plant. They are valuable for determining the relative benefit and better selection of safety enhancements.
Reactor components and structures degrade by exposure to heat, environmental conditions and radiation. It is vital to understand ageing processes to ensure that safety criteria continue to be met.
Nuclear facilities rely on a robust electrical system to power primary and back-up systems required to safely respond to a wide variety of challenging events.
Disruptive technologies for nuclear safety applications
CANDU Owners Group (COG) and the NEA have signed a Memorandum of Understanding to co-operate in research and activities related to pressurised heavy water reactor (PHWR) technology.
Accident analysis and management focusses on understanding the causes and consequences of an accident at a nuclear facility, and on how to manage an accident through prevention and mitigation.
Demonstrating the safety of a nuclear facility requires that the consequences of all possible threats be considered, including external hazards such as severe weather, floods and earthquakes.
This benchmark is based on a well-defined problem concerning a pressurised water reactor (PWR) main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the...