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NEA Document
PBMR Coupled Neutronics/Thermal-Hydraulics Transient Benchmark: The PBMR-400 Core Design - Volume 1: The Benchmark Definition
NEA/NSC/DOC(2013)10

This report defines the “OECD/NEA/NSC PBMR Coupled Neutronics/Thermal-hydraulics Transient Benchmark of the PBMR-400 Core Design”. This chapter gives more information on the day-to-day management of ...

English Nuclear science WPRS Multiphysics Thermal hydraulics and mechanics Reactor physics Multiphysics EGMUP Modelling and simulation Reactor physics NSC Thermal hydraulics Nuclear science Benchmark …
Published date: 19 June 2013
NEA Document
Coupled Neutronic/Thermal-Fluid Benchmark of the MHTGR-350 MW Core Design: Results for the Lattice Physics Exercises
NEA/NSC/R(2019)6

The purpose of this prismatic High Temperature Reactor (HTR) benchmark is to provide a solution set that can be used in future code benchmarking and to better understand the effects induced by the pr...

English Nuclear science WPRS Multiphysics EGTHM Reactor physics Multiphysics EGMUP Reactor physics NSC EGPRS Nuclear science …
Published date: 18 November 2021
NEA Document
Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science EGTHM Reactor physics EGMUP …
Published date: 12 October 2020
NEA Document
A Code to Code Benchmark for High-Temperature Gas-Cooled Reactor Fuel Element Depletion
NEA/NSC/R(2019)1

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 ...

English Nuclear fuel Fuel studies Generation IV reactors Nuclear science WPRS Reactor physics Multiphysics EGMUP Reactor physics Cogeneration NSC Gas-cooled reactors EGPRS Nuclear science Benchmark …
Published date: 18 January 2019
NEA Document
English Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science EGTHM Reactor physics EGMUP …
Published date: 6 December 2017
NEA Document
MOx Depletion Calculation Benchmark
NEA/NSC/R(2016)3

In 2013, the Expert Group on Reactor Physics and Advanced Nuclear Systems (EGRPANS) published a report that investigated fuel depletion effects in a pressurised water reactor (PWR). This was entitled...

English Reactor physics NSC Nuclear science EGPRS WPRS Nuclear science Reactor physics …
Published date: 14 June 2016
NEA Document
International Benchmark on Pressurised Water Reactor Sub-channel and Bundle Tests - Volume III: Departure from nucleate boiling
NEA/NSC/R(2015)7

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...

English Nuclear science WPRS Multiphysics Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics NSC Nuclear science Benchmark Pressurised water reactors …
Published date: 2 October 2015
NEA Document
International Benchmark on Pressurised Water Reactor Sub-channel and Bundle Tests - Volume II: Benchmark results of phase I Void distribution
NEA/NSC/R(2015)4

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...

English Nuclear science WPRS Multiphysics Thermal hydraulics and mechanics EGTHM Reactor physics Reactor physics NSC Nuclear science Benchmark …
Published date: 24 June 2015
NEA Document
Benchmark for Neutronic Analysis of Sodium-cooled Fast Reactor Cores with Various Fuel Types and Core Sizes
NEA/NSC/R(2015)9

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...

English Nuclear fuel Fuel studies Generation IV reactors Nuclear science WPRS Reactor physics Reactor physics Sodium-cooled reactor NSC EGPRS Nuclear science Benchmark …
Published date: 5 November 2015
NEA Document
English Nuclear science Criticality WPNCS WPRS Multiphysics Reactor physics Multiphysics EGMUP Reactor physics Criticality safety NSC Nuclear science …
Published date: 23 February 2016
Other
International Workshop on Nuclear Fuel Modelling to Support Safety and Performance Enhancement for Water-Cooled Reactors, 7-9 March 2017 - Announcement

Announcement for the nternational Workshop on Nuclear Fuel Modelling to Support Safety and Performance Enhancement for Water-Cooled Reactors, 7-9 March 2017

Material science WPMM NSC Nuclear science Materials science …
Published date: 5 March 2020
Event
International Workshop on Nuclear Fuel Modelling to Support Safety and Performance Enhancement for Water-Cooled Reactors
7 - 9 March 2017
OECD Conference Centre, 2 rue André Pascal, Paris, France

Advanced techniques for fuel modelling have progressed considerably in the last decade in part aided due to progress in high-performance computational capability. At the engineering scale, this has r...

Material science WPMM NSC Nuclear science Materials science …
Published date: 5 March 2020
Activity
WPMM Expert Group on Multi-scale Modelling Methods (EGM3)

Under the guidance of the Nuclear Science Committee (NSC) and under the mandate of the Working Party on Multi-scale Modelling of Materials (WPMM), the scope of the Expert Group on Multi-scale Modelli...

Material science WPMM NSC Nuclear science Materials science EGM3 …
Published date: 4 March 2020
News
Reactor physics News brief NSC Nuclear science Radiation shielding EGPRS SINBAD WPRS Reactor physics …
Published date: 7 April 2023
Activity
DATabase for IFpe (DATIF)

Development started on DATIF, the DATabase for IFpe, in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the...

Nuclear fuel Physics Fuel studies NSC EGRFP Databases Ancillary data Reactor physics Integral experiments …
Published date: 12 April 2023
News
Internationally recognised thermodynamic data to advance nuclear materials knowledge

International experts gathered at the NEA for the commencement of the third phase TAF-ID on 16-17 February 2023.

News brief Fuel studies Nuclear science Materials science Nuclear data Joint project Material science NSC Thermodynamic data TAF-ID …
Published date: 24 February 2023
News
News brief Fuel studies Nuclear science Materials science Fukushima Joint project Reactor fuel performance Material science NSC Thermodynamic data TCOFF …
Published date: 24 February 2023
News
Expert groups on structural and fuel materials meet to advance materials science activities

Expert groups on structural and fuel materials meet to advance materials science activities

News brief Fuel studies Nuclear science Materials science Databases Material science NSC WPFM Accident tolerant fuels …
Published date: 24 February 2023
News
News brief NSC Nuclear science SINBAD WPRS Multiphysics Nuclear science Benchmark Multiphysics …
Published date: 17 March 2023
News
Members of NEA Second Framework for Irradiation Experiments (FIDES-II) meet in Czech Republic

Members of FIDES-II from 12 countries assembled in Prague, Czech Republic, on 17-21 April 2023 for meetings of its Technical Advisory Group and Governing Board.

Fuel in nuclear safety Nuclear fuel News brief Nuclear science Nuclear safety FIDES Reactor fuel performance NSC Nuclear science Accident Tolerant Fuels Accident tolerant fuels …
Published date: 21 April 2023