The workshop on the Approaches to design, implementation and operation of electrical systems for beyond design basis equipment and management of geomagnetically induced currents in electrical systems...
RASPLAV-A-Salt Facility, EREC.
The RASPLAV* Project was regarded as a successor to the Three Mile Island Vessel Investigation Project (TMI-VIP) completed in 1993. The TMI-VIP Project was set up t...
Control room, PAKS NPP.
Software-based systems are used and retrofitted in operating nuclear power plants worldwide. The failure modes of both hardware and software in these systems are to some ext...
Post-test view inside OLHF-4 vessel showing penetrations and resolidified weld material at the vessel bottom.
During a severe accident, the lower head of a reactor pressure vessel (RPV) can be subj...
EPICUR facility, IRSN.
The STEM Project was initiated with a first phase in 20...
Experts from 16 countries met on 13-15 September for the 24th annual Working Group on Fuel Safety GFS meeting in Paris.
Photo: RBHT Test Facility. US NRC.
Modelling reactor core behaviour under accident conditions with delayed re-introduction of cooling water (commonly referred to as reflood) is a challenge for safety...
While there is a growing interest in the deployment of small modular reactors (SMRs) as a promising option to help mitigate climate change, further international efforts are needed to accelerate the ...
The Committee on the Safety of Nuclear Installations (CSNI) is responsible for NEA programmes and activities that support maintaining and advancing the scientific and technical knowledge base of the ...
View of the RASPLAV-3 Facility.
The Material Scaling (MASCA) Project was a follow-up of the RASPLAV Project and investigated in-vessel phenomena during a severe accident with core melt. Specifica...
Scheme of the PSB-VVER facility, EREC
The NEA PSB-VVER project provided unique and useful experimental data for code validation using the PSB-VVER test facility. The PSB-VVER facility is a large-scal...
PKL facility. Photo: FRAMATOME, Germany
The Primärkreislauf-Versuchsanlage (Primary Coolant Loop Test Facility [PKL]) is a facility owned and operated by Framatome GmbH (formerly AREVA NP) in Erlange...
View of the ATLAS experimental loop. KAERI, KoreaThe Advanced Thermal-hydraulic Test Loop for Accident Simulation (ATLAS) Project was referenced in The Fukushima Daiichi Nuclear Power Plant Accident...
Scheme of the ROSA LSTF facility, JAEA
The Rig-of-safety Assessment (ROSA) Project aimed to resolve issues in thermal-hydraulics analyses relevant to light water reactor (LWR) safety using the Japa...
General view of the EREC test facility BC V-213, source: EREC
There are several VVER-440/213* type nuclear power plants operating in the Czech Republic, Hungary, Slovak Republic, Russia and Ukraine...
The OECD NEA RASPLAV Project provided experiments with prototypical material and data on the behavior of molten core material (corium) in the reactor pressure vessel lower head during a severe accide...
Image: Microscopic examination of U-bearing particles collected at Fukushima-Daiichi, JAEA
The Thermodynamic Characterisation of Fuel Debris and Fission Products ...
Electrical cable fire test, IRSN.
The NEA PRISME project addressed in a series of 3 phases from 2006 till 2022 fire risk research. Operating experience shows that fire is one of the highest risks i...
In a core melt accident, if the molten core is not retained in-vessel despite severe accident mitigation actions, the core debris will relocate to the reactor cavity region and interact with the stru...