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

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...

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...

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

IRPhE Handbook 2019 Edition - Contents

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

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....

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...

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

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

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...

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...

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...

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

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) annual meeting, 15-19 February 2021.

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...

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...

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...

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.

The International Reactor Physics Experiment Evaluation (IRPhE) Technical Review Group provides the nuclear community with qualified benchmark data sets by collecting reactor physics experimental dat...

The international benchmark concerned pebble bed modular reactor (PBMR) coupled neutronics/thermal-hydraulics transients based on the PBMR-400MW design.

Neutron noise analysis can be defined as the direct measurement of the kinetics of a nuclear core. This page describes some of the NEA's previous activities on neutron noise analysis in nuclear power...

For nuclear utility companies that opt to reprocess spent fuel, recycle it or do both, one of the main pertinent issues is plutonium recycling.

Helium-cooled very high-temperature gas reactors are highlighted as a key technology with the potential to improve the competitiveness of nuclear energy within the Generation IV International Forum (...

ICSBEP, SINBAD AND IRPhEP Technical Review Group meetings, October 2021.

The expert group provided advice to the Working Party on Scientific Issues of Reactor Systems (WPRS) on the scientific development needs (data and methods, validation experiments, scenario studies) o...

The Expert Group on Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF) dealt with the various aspects of the modelling and design of accelerator shield systems and radiatio...

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...

Under the guidance of the  Nuclear Science Committee (NSC) , the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) studies the reactor physics, fuel performance, ...

The IRPhEP Database and Analysis Tool (IDAT) was first released in 2013 and is included on the IRPhE Handbook DVD. This database and corresponding user interface allows easy access to handbook inform...

The aim of the benchmark is to improve understanding and modelling of pellet-cladding mechanical interaction (PCMI) amongst NEA member organisations. This is achieved by comparing PCMI predictions of...

Collected sources of primary documentation for reactor physics benchmarks.

The annual Benchmark Workshop of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems was hosted by CEA Cadarache in Aix-en-Provence. During the week of 30 May to 3 June...

WPRS gathered 172 experts from 22 countries at the annual Benchmark Workshop.

High-temperature gas-cooled reactors (HTGRs), also known as very-high-temperature reactors (VHTR) are Generation IV reactors that can operate at very high temperatures and use a graphite-moderated ga...

The International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE) contains reactor physics benchmark specifications that have been derived from experiments that were performed at ...

The goal of the Benchmark for Uncertainty Analysis in Best-Estimate Modelling for Design, Operation and Safety Analysis of Light Water Reactors (LWR-UAM) is to determine the uncertainty in light wate...

The Boiling Water Reactor Turbine Trip (BWRTT) Benchmark was established to challenge the coupled system thermal-hydraulic/neutron kinetics codes against a Peach-Bottom-2 (a GE-designed BWR/4) turbin...

This benchmark was a continuation of the V1000CT activities and defined a coupled code problem for further validation of thermal-hydraulics system codes for application with Russian-designed VVER-100...

PWR MOX/UO2 Core Transient Benchmark

To ensure reliable modelling of neutron physics within a state-of-the-art transient code, the neutron kinetics part of such a code should be based on the full-scale calculation of the space-time neu...

Building on the NEA BFBT and PSBT benchmarks, McMaster University, in collaboration with North Carolina State University, launched a CANDU thermal-hydraulic benchmark under the WPRS Expert Group on U...

The Liquid Metal Fast Reactor (LFMR) is one of the next generation reactor designs. This benchmark consists of steady-state numerical predictions of Texas A&M University (TAMU) separate effect tests ...

Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS) the expert group performs specific tasks associated with fuel performance aspects of pr...

Created in 2019, under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS) the expert group will perform specific tasks associated with core thermal-hydraulics aspects of...

The Expert Group on Reactor Systems Multi-Physics (EGMUP) advances the state of the art in establishing processes and procedures for certifying experimental data and benchmarking multi-physics multi-...

Under the guidance of the Working Party on Scientific Issues and Uncertainty Analysis of Reactor Systems (WPRS), the Expert Group on Physics of Reactor Systems (EGPRS) performs specific tasks associa...

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 overall objective of the VVER-1000 Coolant Transient (V1000CT) Benchmark was to assess computer codes used in the safety analysis of water-water energetic reactor (VVER) power plants, specificall...