In the years 2018 to 2020, the company VUJE, a.s. supplied the system for monitoring the  concentration of hydrogen in the containment for beyond design basis accidents in Rivne Nuclear Power Plant (RNPP) Units 3 and 4. The system was delivered to RNPP as part of the implementation of measures within the Complex Consolidated Safety Upgrade Program for the Ukraine Nuclear Power Plants.

Jacobs, the global technology-forward solutions company, is supporting the development of a new type of nuclear power plant.

VUJE completed delivery of brand-new manipulator for remote controlled plugging of VVER-440 steam generator heat exchanging tubes. Based on extensive experience with development of this kind of equipment VUJE presented turnkey solution, customized to Hungarian Paks NPP requirements.

Following its acquisition of Wood Nuclear in March 2020, global technology-forward solutions company Jacobs is the UK member of Eurosafe

Research by an international consortium could lead to extensions in the operational lifespan of nuclear power plants around the world. The INCEFA-SCALE programme aims to reduce uncertainties about how critical components will perform when subjected to the harsh conditions inside operational reactors.

One of the key duties of a nuclear safety authority is to ascertain the nuclear facility safety.

MYRRHA (Multipurpose hYbrid Research Reactor for High-tec Applications) is a unique highly innovative prototype of a nuclear reactor driven by a high power linear accelerator. It will be designed to operate in both critical (no accelerator needed) and subcritical mode. MYRRHA has a fast spectrum core cooled by Lead Bismuth Eutectic (LBE).

The recent stress corrosion cracking (SCC) in Alloy 182 in reactor pressure vessel nozzles, reactor internal attachment or penetrations dissimilar metal welds in boiling water reactors (BWRs) represent a serious potential safety concern.

Russian federal nuclear safety rules and regulations ‘Basic Safety Provisions for Nuclear Power Plants’ (NP-001-15) establish a requirement to complement the safety analysis for a nuclear power plant with estimation of errors and uncertainties in the obtained results.

A leak suspected to have been caused by high cycle thermal fatigue due to fluctuating axial motion of a swirl penetration front end has been detected in early 2018 in a non-isolable Reactor Coolant System branch at the Doel 1 Nuclear Power Plant (Belgium).