The Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, and radiation transport and shielding in present and future nu...

The main mission of the Working Group on Fuel Safety (WGFS) is to advance the current understanding and address cross-cutting issues related to fuel behaviour in accident conditions, including work o...

DATIF, the DATabase for IFpe, was first developed in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the NE...

The Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) studies advanced nuclear fuel cycles, including fuel cycle scenarios, innovative fuels and materials, separation chemistry, waste...

Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Fuel Recycling and Waste Technology (EGFRW) focuses on the separation processes releva...

Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) meeting, 8 June 2021.

The TAF-ID public version contains only data already published in open literature. Currently, the following systems are available in the public version:

• oxide-carbide fuel (U-Pu-O-C, released Decemb...

Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Innovative Fuel Elements (EGIFE) conducts joint and comparative studies to identify te...

Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Reactor Coolants and Components Technology (EGCoCoT) undertakes activities with the go...

Under the guidance of the  Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) , the Expert Group on Advanced Fuel Cycle Scenarios (EGAFCS) studies the needs associated with the transit...

Uranium is the raw material used for nuclear energy generation. It is mined and further processed to make up the highly engineered fuel that is used in nuclear reactors.

International Fuel Performance Experiments (IFPE) is the public domain database on nuclear fuel performance experiments for the purpose of code development and validation.

Understanding fuel performance is a key condition for successful reactor operation. Scientific knowledge in this domain was conceived by experimental tests encoded into software routines to ensure ac...

Average fuel burn-up in light water reactors (LWRs) has steadily increased with time as technological advances have been made. The practical limit is currently in the region of 50 GWd/t. The main dri...

This publication provides an introduction to minor actinide nuclear properties and discusses some of the arguments in favour of minor actinide recycling, as well as the potential role of thermal reac...

Sodium fast reactors offer the most promising type of reactors to achieve such Generation IV goals at a reasonable time scale given the experience accumulated over the years. However, it is recognise...

The high-temperature gas-cooled reactor (HTGR) is a Generation IV reactor concept that uses a graphitemoderated gas-cooled nuclear reactor with a once-through uranium fuel cycle. This design permits ...

The Expert Group on Reactor-based Plutonium Disposition (TFRPD) dealt with the status and trends of reactor physics, fuel performance and fuel cycle issues related to the disposition of weapons-grade...

Historically, average discharge burn-ups in light water reactors (LWRs) have steadily increased with time as experience has accumulated and technological developments have progressed. The main benefi...

The nuclear fuel cycle is the chain of processes whereby nuclear fuel is prepared and managed before and after its use in a reactor.

The expert group monitored the feedback from version 0 of the Lead-bismuth eutectic (LBE) handbook, collected, analysed and checked the consistency of expected new results from ongoing heavy liquid m...

The expert group conducts joint and comparative studies to support the development, selection and characterisation of innovative structural materials that can be implemented in advanced nuclear fuel ...

The task force developed best practice guidelines by performing a benchmark study on thermo-hydraulic modelling of heavy liquid metal coolant, e.g. lead and lead-bismuth eutectic (LBE) alloy.

The expert group primarily acted as a forum for scientific and technical information exchange on advanced light water reactor (LWR) fuels with enhanced accident tolerance.

The relevance of the IFPE Database to the modelling of WWER-type fuel behaviour, 6^th International Conference on WWER Fuel Performance, Modelling and Experimental Support, Albena, Bulgaria, September...

OECD Nuclear Energy Agency (NEA) and US Nuclear Regulatory Commission PWR MOX/UO2 Core Transient Benchmark Final Specifications, Revision 2 (2003)

NEA News is the professional journal of the Nuclear Energy Agency (NEA). It features articles on the latest nuclear energy issues concerning the economic and technical aspects of nuclear energy, nucl...

NEA News is the professional journal of the Nuclear Energy Agency (NEA). It features articles on the latest nuclear energy issues concerning the economic and technical aspects of nuclear energy, nucl...

The TCOFF project provides a framework for the exchange of technical information on topics related to thermodynamic databases available for modelling the fuel/core degradation process, which include ...

Spent Nuclear Fuel Reprocessing Flowsheet

The implementation of advanced nuclear systems requires that new technologies associated with the back end of the fuel cycle are developed. The separation of minor actinides from other fuel component...

As part of the development of advanced nuclear systems, including accelerator-driven systems (ADS) proposed for high-level radioactive waste transmutation and generation IV reactors, heavy liquid met...

Heavy liquid metals such as lead or lead-bismuth have been proposed and investigated as coolants for fast reactors since the 1950s. More recently, there has been renewed interest worldwide in the use...

Many countries have been performing a wide range of research on the partitioning and transmutation (P&T) of minor actinides and fission products. The aim is to provide greater flexibility in terms of...

Future nuclear fuel cycles could effectively address radioactive waste issues with the implementation of partitioning and transmutation (P&T). Previous studies have defined the infrastructure require...

Regional strategies can provide a useful framework for implementing innovative nuclear fuel cycles. The appropriate sharing of efforts and facilities among different countries is necessary in today’s...

Future fuel cycle characteristics, feasibility and acceptability will be crucial for the continued development of nuclear energy, especially in the post-Fukushima context. Fuel cycle choices have bot...

Development of innovative fuels such as homogeneous and heterogeneous fuels, ADS fuels, and oxide, metal, nitride and carbide fuels is an important stage in the implementation process of advanced nuc...

Materials performance is critical to the safe and economic operation of any nuclear system. As the international community pursues the development of Generation IV reactor concepts and accelerator-dr...