Graphite used in nuclear plants must be disposed of properly. Prolonged aging, even at room temperature, can lead to the formation of different species, such as graphite oxide, which has the possibility of being dispersed into the environment much more easily and this entails a risk that must be taken into consideration

Clearance measurement should be performed as a conformity assessment of the evaluated contamination values to the regulatory limit, considering the measurement’s uncertainty, including the uncertainty of the ratio of the activity concentration of the difficult to measure nuclide to that of the key nuclide. The key issues for the treatment of these uncertainty were summarized.

Advanced concepts of CANDU fuel bundles with more than 37 elements are analyzed comparatively to the 37-rods standard fuel bundle design from the safety performance point of view.

Scientists of Lithuanian Energy Institute have been developing an open-source turbulent combustion solver flameFoam, based on OpenFOAM toolkit. Code to code analysis and comparisons with experiments showed that flameFoam mostly corresponds to the state-of-the-art currently achieved in the field.

Application of statistical non-parametric methods to radioxenon distributions in atmosphere in order to study the atmospheric background fluctuations and the influence of anthropogenic activities.

NRA Secretariat experts developed an empirical method for estimating source vicinity ground-motion levels on hard bedrock and annual exceedance probabilities for inland crustal earthquakes with sources difficult to identify in advance.

For the examination of plasma and impurity transport in the DT experimental campaign, energy balance, dependency on discharge, and the time evolution of radiation loss profiles are provided by LEI scientists. Indeed, the record braking pulse  is also being analyzed here at LEI.

Safety Analyses of SMR with Passive Mitigation strategies - Severe Accident (SASPAM-SA) project proposal has been submitted and has been founded in HORIZON-EURATOM-2021-NRT-01-01, “Safety of operating nuclear power plants and research reactors”. The project is coordinated by ENEA (Italy) and its key objective  is to investigate the applicability and transfer of the operating large-LWR reactor knowledge and know-how to the near-term deployment of iPWR, in the view of severe accident  and emergency planning zone  European licensing analyses needs.

NRA conducted tube burst tests and post-test analyses on high-burnup spent nuclear fuel claddings to investigate the condition for the occurrence of macroscopic hydrogen-induced ductile-brittle transition at operational temperatures with quantitative consideration of precipitated Zr hydrides' morphology.

We have developed a debris bed formation prediction method that takes into account accident scenarios and physical properties by providing THERMOS with the analysis results in MELCOR.