The working meeting “Towards Nuclear Fuel Modelling in the Various Reactor Types across Europe” was held in Karlsruhe (Germany). The event was organized by JRC (Joint Research Centre, EC).
The number of relevant issues were considered during the meeting, in particular, the status of TRANSURANUS code, fuel modeling for light water reactors under normal operation and design-basis accidents, nuclear fuel storage, modeling of advanced fuel types. The coupling of calculation codes was considered separately.
Experts of JRC, which is TRANSURANUS code developer, pointed out that the code is currently used in 45 organizations. The main areas of code development include the extension and improvement of the libraries of fuel cladding and pellet materials, fuel for fast reactors, combination of the code with other software (“multi-physical” development of computer codes), code update to analyze sensitivity and uncertainties. Besides, the most recent code upgrades included into official release, development of graphical interface, development prospects for sensitivity and uncertainty analysis in TRANSURANUS code were considered.
Maksym Yeremenko, Head of SSTC NRS Nuclear Installation Neutronic Processes Department Laboratory, provided meeting participants with Ukrainian experience in verification calculations for the review of safety justification data related to the introduction of new VVER-1000 fuel (FA-WR), new fuel for VVR-М research reactor (Kyiv) and scientific activities carried out within the FUMAC project.
The expert highlighted current results of activities under the license agreement, which provides for the continuation of TRANSURANUS code optimization for calculation of gadolinium fuel rod and consists in calculation of additional cross-section libraries for real and advanced VVER-440 and VVER-1000 fuel. These are FAA, FAA-12 and FA-WR fuel for VVER-1000; second and third generation fuel for VVER-440.
The reports presented during meeting are of high priority for TRANSURANUS code users, in particular for the SSTC NRS. The information obtained at the meeting will be used in future state reviews of nuclear and radiation safety of current fuel loadings, documents on the implementation of new nuclear fuel and during scientific activities on Ukrainian NPP safety improvement.