First Information Exchange Meeting on the Nuclear Production of Hydrogen, Paris, France, 2-3 October, 2000 - Programme and abstracts

Third Information Exchange Meeting on the Nuclear Production of Hydrogen including Second HTTR Workshop, Japan Atomic Energy Agency (JAEA), Oarai, Japan, 5 - 7 October 2005 - Programme

The quality of the isotopic composition of plutonium fuel degrades as the number of recycles increases in thermal reactors, requiring an increase in the total loading necessary in mixed plutonium-ura...

The Subgroup on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM) was formed to check the use of best-estimate codes and data....

Multiphysics are simulations using computer applications or software to couple multiple physical events in order to predict or validate the physical real-world outcome.

IRPhE Handbook 2019 Edition - Contents

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

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 expert group works in co-ordination with Working Party on Scientific Issues of Reactor Systems (WPRS) [including the IRPhE Project], Working Party on Scientific Issues of the Fuel Cycle (WPFC) an...

NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 19-21 February 2020.

Under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS), the expert group performed specific tasks associated with radiation transport and shielding aspects of current ...

Current activities related to EGUAM.

Chart showing the benchmarks related to EGUAM that have now been completed.

Questions relating to the space, time end energy distribution of neutrons and radiation in different media are the domain of reactor physics.

ICSBEP, SINBAD AND IRPhEP Technical Review Group meetings

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 ...

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 need to refine models for best-estimate calculations based on good-quality experimental data has arisen for various nuclear applications. One of the most extensive and valuable databases availabl...

The objective of the benchmark was twofold. First, the benchmark aimed to evaluate currently available computational approaches in an effort to understand the strengths and weaknesses of current ther...

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...

Based on the success of the OECD/NRC BFBT Benchmark, Japan released data based on the NUPEC PWR Sub-channel and Bundle Tests (PSBT) Benchmark and asked Pennsylvania State University (PSU) in the Unit...

This report provides the specification for the uncertainty exercises of the international OECD/NEA, NRC and NUPEC BFBT benchmark problem including the elemental task. The specification was prepared j...

The NEA Nuclear Science Committee (NSC) had previously organised three information exchange meetings to discuss scientific and strategic matters pertaining to the nuclear production of hydrogen. Earl...

In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and co...

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...

Refined models for best-estimate calculations based on good-quality experimental data can improve the understanding of phenomena and the quantification of margins for operating nuclear power reactors...

In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and co...

The NEA Nuclear Science Committee (NSC) had organised two previous information exchange meetings on the nuclear production of hydrogen. The last of these meetings was held in October 2003, where deve...

As growing demand for energy has prompted ever-increasing use of fossil fuels, the resulting issues of energy security and climate change have in turn led to renewed interest in the use of hydrogen a...

21-22 January 2003, Barcelona, Spain

In the field of coupled neutronics/thermal-hydraulics computation there is a need to enhance scientific knowledge in order to develop advanced modelling techniques for new nuclear technologies and co...

6 October 2002, Seoul, Korea

Although the recycling of plutonium as thermal mixed-oxide (MOX) fuel in pressurised water reactors (PWRs) is now well-established on a commercial scale, many physics questions remain. The main quest...