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Joint project
Dragon Project

View of Dragon Reactor. Photo: AEA Technology.

In 1959, twelve OECD countries began the Dragon Reactor Experiment (DRE) to build a reactor at Winfrith in Dorset, United Kingdom. The Dragon was the fi...

Criticality safety Generation IV reactors Nuclear science Gas-cooled reactors Reactor physics …
Published date: 14 October 2022
Joint project
Loss of Forced Coolant (LOFC) Project

JAEA  High-temperature Engineering Test Reactor Photo: Japan Atomic Energy Agency (JAEA)

 

The Committee on the Safety of Nuclear Installations (CSNI) Task Group on Advanced Reactor Experimental Facil...

Generation IV reactors Gas-cooled reactors Accident analysis and management Nuclear safety research CSNI …
Published date: 11 October 2022
Activity
High-Temperature Gas-Cooled Reactors

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...

Cogeneration Generation IV reactors Nuclear science Gas-cooled reactors Multiphysics Reactor physics …
Published date: 22 June 2022
Publications and Reports
High-temperature Gas-cooled Reactors and Industrial Heat Applications

Reducing industrial carbon emissions is one of the most difficult challenges on the path to net zero by 2050 due to the magnitude of greenhouse gas emissions from the industrial sector and technical ...

English SMR Cogeneration Generation IV reactors Gas-cooled reactors Hydrogen Nuclear technology …
Published date: 16 June 2022
Event
High-temperature Gas-cooled Reactors and Industrial Heat Applications - report launch
16 June 2022
Online webinar

Reducing industrial carbon emissions is one of the most difficult challenges on the path to net zero by 2050, due to the magnitude of greenhouse gas emissions from the industrial sector and technolog...

Generation IV reactors Gas-cooled reactors Nuclear technology
Published date: 1 June 2022
Activity
Benchmark of the Modular High-Temperature Gas-Cooled Reactor-350 MW Core Design

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 (...

Gas-cooled reactors Reactor physics
Published date: 20 September 2021
Publications and Reports
Nuclear Safety Research Support Facilities for Existing and Advanced Reactors: 2021 Update

Experimental facilities in nuclear energy are key to addressing safety issues. The recent loss of some critical infrastructure, from facilities to industry expertise, has therefore become a concern f...

English Boiling water reactors Molten salt reactors Nuclear safety Light water reactors Safety Advanced reactors Safety research Sodium-cooled reactor Gas-cooled reactors Pressurised heavy water reactors Pressurised water reactors …
Published date: 8 September 2021
Activity
Pebble Bed Modular Reactor (PBMR) Coupled Neutronics/Thermal-hydraulics Transients Benchmark - PBMR-400 Core Design

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

SMR Gas-cooled reactors Thermal hydraulics Verification Multiphysics Benchmark Reactor physics Multiphysics …
Published date: 26 July 2021
Publications and Reports
Physics of Plutonium Recycling - Volume III

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...

English Nuclear science Plutonium Liquid metal reactors Advanced reactors Reactor physics Recycling and reuse Reactor physics NSC Gas-cooled reactors Fuel cycle technology Fuel cycle physics and chemistry Pressurised water reactors …
Published date: 17 November 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