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Joint Research Centre

TRANSURANUS nuclear fuel performance code

TRANSURANUS is a software used worldwide for assessing the safety of nuclear fuel rods in current and advanced reactor types.

About

Workshops and trainings

The JRC organises every other year an international workshop for TRANSURANUS developers and users to disseminate knowledge and obtain feedback for further developments. 

The JRC provides regular training courses in collaboration with universities for students and staff members of organisations with a valid user license. 

Scientific actions and support

Supporting nuclear safety in the EU

TRANSURANUS supports nuclear safety through reliable simulation of fuel behaviour under normal operation, transient conditions and accident scenarios. It is used in fuel licensing and regulatory review processes. Its adoption by most European Technical Safety Organizations Network (ETSON) members highlights its position as a reference tool for nuclear safety in Europe. 

Support Industrial Alliance for SMRs

The TRANSURANUS user network includes SMR and Advanced Modular Reactors (AMR) developers. Recent applications have demonstrated the code’s capability to support safety and performance assessments of advanced fuels for innovative reactor designs, including concepts considered within the framework of the European Industrial Alliance on SMRs. This positions TRANSURANUS as a valuable tool for evaluating fuel behaviour under conditions relevant to advanced reactor deployment. The alliance was created in 2024 by the JRC together with Directorate-General for Energy (DG ENER), Directorate-General for Internal Market, Industry, Entrepreneurship and SMEs (DG GROW) and Directorate-General for Research and Innovation (DG RTD).

Spent Fuel Managememt

During dry storage and disposal of irradiated nuclear fuel rods, the helium build up and release and cladding degrading mechanisms can affect fuel rod state. JRC initiated collaboration with several EU organisations to extend the TRANSURANUS capabilities for simulation of irradiated nuclear fuel pins during long term storage.

Education and training – developing skills

For more than a decade, TRANSURANUS has also been used extensively in education and training through training courses and workshops with the support of organizations such as the International Atomic Energy Agency (IAEA) and the European Nuclear Education Network (ENEN). The code serves as a reference tool for educating students, researchers and professionals in nuclear fuel behaviour modelling and simulation.

Impact and results

As a widely recognized fuel safety modelling tool, TRANSURANUS is used for fuel safety verifications by practically all nuclear EU Member States.  

It is therefore essential to train staff from nuclear safety authorities, technical support organisations and the nuclear industry in both the operational functionalities and the scientific basis of the TRANSURANUS code.  

To ensure this, the JRC trains around 20 nuclear staff each year, contributing to the development and maintenance of high-level skills and competencies in the field of nuclear fuel safety across Europe. 

Through its contribution, the JRC directly supports Member States in the implementation of their nuclear safety policies.

Policy background

TRANSURANUS supports EU nuclear policy under the Euratom framework and the JRC Work Programme 2025-2027.

  • Nuclear safety and skills: The JRC contributes to the safe operation of nuclear reactors through independent technical assessments and research on nuclear fuel behaviour, while also supporting the preservation and development of nuclear skills within Europe.
  • Small modular reactors: The JRC provides technical evidence on the safety, performance and sustainability of AMR and SMR technologies, and actively supports the European Industrial Alliance on SMRs.
  • EU decarbonisation goals: The JRC supports evidence-based policymaking on the role of nuclear energy in Europe’s clean energy transition, including assessments of how advanced nuclear systems may contribute to a stable, low-carbon and diversified energy mix. 

Related Publications

Publications
Journal of Nuclear Materials
  • General publications
  • 16 April 2026
A review of fuel performance modelling

Nuclear fuel performance modelling is performed using dedicated computer codes. Such codes exist for many fuel types and are used for a variety of purposes, including design optimization, experiment planning and interpretation, and safety analysis.

JRC Publications Repository - A review of fuel performance modelling

Progress in Nuclear Energy cover
  • General publications
  • 16 April 2026
Modelling and assessment of thermophysical properties of Am-bearing fuels for transmutation purposes in fast reactors

Minor Actinides (MAs) are produced inside nuclear reactor fuels under irradiation and are responsible of large part of the waste radiotoxicity. Partitioning and Transmutation (P&T) is identified as the strategy that can relax constraints on geological disposal, since transmutation of MAs via critical or subcritical fast spectrum irradiation facilities like MYRRHA is a valid path to reduce the waste hazard. 

Modelling and assessment of thermophysical properties of Am-bearing fuels for transmutation purposes in fast reactors - ScienceDirect

 Annals of Nuclear Energy cover
  • General publications
  • 16 April 2026
Fuel performance modelling of Cr-coated Zircaloy cladding under DBA/LOCA conditions

Chromium coatings are being developed for advanced technology fuel (ATF) claddings, offering negligible corrosion during normal operation, improved resistance to high-temperature steam oxidation, and superior high-temperature strength, the latter two being of utmost relevance during design basis accidents (DBAs). Demonstrating the improved response of Cr-coated Zircaloy requires the development or extension of fuel performance codes to coating simulations.

JRC Publications Repository - Fuel performance modelling of Cr-coated Zircaloy under DBA/LOCA conditions

Annals of Nuclear Energy
  • General publications
  • 16 April 2026
Comparison of Advanced-Technology-Fuel options in soluble boron-free Small Modular Reactors

Water-cooled Small Modular Reactors (SMRs) have gained significant attention as they could be modularised, standardised, and factory-fabricated to reduce capital cost and improve passive safety.

Comparison of Advanced-Technology-Fuel options in soluble boron-free Small Modular Reactors - ScienceDirect

Nuclear Engineering and Design
  • General publications
  • 16 April 2026
High-fidelity and high-resolution simulation of two different rod ejection accidents in a NuScale-like small modular reactor with conventional and accident tolerant fuels

This work presents a high-fidelity pin-by-pin simulation approach for a NuScale-like Small Modular Reactor core during a rod ejection accident (REA). 

https://publications.jrc.ec.europa.eu/repository/handle/JRC140367 

Related portfolios

TRANSURANUS supports the scientific portfolios:

Contact us

For any additional information or enquiries please contact us at:

Organisation
DG JRC Directorate G Unit G.5
Email
JRC-TRANSURANUSatec [dot] europa [dot] eu