Fluoride salt-cooled high-temperature reactors (FHRs), cooled with liquid (molten) salt, fueled with TRISO-based fuel are a potential molten salt reactor (MSR) design.

This benchmark focuses on FHR reactors with plates and triso fuel. Several phases are planned, starting with neutronics on a simple fuel element simulation without burn-up, and gradually extending to...

In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for Boiling Water Reactor (BWR) fuel bundles. This international benchmark, bas...

The expert group critically reviewed integral experiments for validating minor actinide (MA) nuclear data, recommended additional integral experiments needed for validating MA nuclear data and invest...

NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 15-19 February 2021.

A sodium-cooled fast reactor (SFR) is a fast neutron reactor that uses molten sodium metal as a coolant. Sodium-cooled Fast Reactors (SFRs) are the most promising type of reactors to achieve Generati...

NEA Working Party on Scientific Issues of Reactor Systems (WPRS) workshops, 7-15 December 2020.

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...

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...

Thermal hydraulics and mechanics deals with the physics and mechanics of the flow and energetic transfer of liquids, and its interactions with the structures around them in large complex systems, suc...

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.