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 ...
Published date:
19 June 2013
Recently developed best-estimate computer code systems for modelling 3-D coupled neutronics/thermal-hydraulics transients in nuclear reactors need to be validated against results from experiments and...
Published date:
5 October 2010
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...
Published date:
16 November 2007
NEA/NSC/R(2020)7
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...
Published date:
2 December 2021
NEA/NSC/R(2020)6
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...
Published date:
1 June 2021
NEA/NSC/R(2020)5
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...
Published date:
4 June 2021
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...
Published date:
18 November 2021
Published date:
12 October 2020
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 ...
Published date:
18 January 2019
Published date:
6 December 2017
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...
Published date:
14 June 2016
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...
Published date:
2 October 2015
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...
Published date:
24 June 2015
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...
Published date:
5 November 2015
Accident-tolerant fuels may offer opportunities to enhance the safety and competitiveness of commercial nuclear power plants.
Published date:
16 December 2019
Criticality safety relates to accident prevention and protection from an uncontrolled nuclear fission chain reaction, or a criticality accident.
Published date:
2 December 2019
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...
Published date:
10 December 2020
Published date:
23 February 2016
Published date:
21 February 2023
Published date:
21 February 2023
Phase III - “How to transparently implement and post-assess decisions for their holism, inclusiveness and sustainability?”
Published date:
21 February 2023
This brochure is published in commemoration of the 20th anniversary of the NEA Regulators' Forum (RF). The document describes the history of RF, its major milestones, achievements, and vision for the...
Published date:
23 February 2023
The TAF-ID public version contains only data already published in open literature. Currently, the following systems are available in the public version:
- oxide-carbide fuel (U-Pu-O-C, released Decemb...
Published date:
23 February 2023
NEA webinars explore a common understanding of optimisation as an approach to decision making.
Published date:
8 February 2023
The NEA Working Party on Information, Data and Knowledge Management discussed the topic of AI and data preservation during their third plenary meeting on 7-8 February 2023.
Published date:
24 February 2023
Towards an All‑Hazards Approach to Emergency Preparedness and Response: Lessons Learnt from Non‑Nuclear Events, Friday, 12 January 2018 at 13:30-14:30 Paris time
Published date:
8 June 2020
NEA Director-General Magwood shares his forecast for the biggest developments and challenges in the nuclear energy sector in 2023.
Published date:
3 February 2023
NEA delegation was in Japan for a series of bilateral meetings and events with students.
Published date:
27 February 2023
The goal of the LOCA-MIR experiments is to study the behaviour of high burnup, gadolinia-doped fuel under design-basis LOCA conditions.
Published date:
12 August 2022
CHIP experimental facility to study fission product transport and deposition in the primary circuit. Photo: IRSN
Following several years of experimental research in the field of source terms analysis...
Published date:
21 October 2022
Units 1 and 2 End of Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (4th October, 2011). Photo: Tokyo Electric Power Company Holdings
The Benchmark Study of the Acci...
Published date:
25 November 2022
End state of debris in the units 1-3 of Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings. Photo: Japan Atomic Energy Agency
The Preparatory Study on Analysis of Fuel D...
Published date:
25 November 2022
Investigation for damage condition and radiation dose in Unit 3 at Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (December 2019). Photo: Japan Nuclear Regulation Au...
Published date:
19 October 2022
Appearance of Unit 1 and 2 reactor buildings at Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (June 2022). Photo: Japan Nuclear Regulation Authority
The FACE projec...
Published date:
17 October 2022
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...
Published date:
14 October 2022
Published date:
2 March 2023
NEA Framework for Irradiation Experiments (FIDES) flyer (October 2019)
Published date:
10 January 2020
Kick-off meeting preparation for the Framework for Irradiation Experiments (FIDES) Joint Experimental Programmes (JEEPs) - List of participants
Published date:
27 February 2020
Announcement for the nternational Workshop on Nuclear Fuel Modelling to Support Safety and Performance Enhancement for Water-Cooled Reactors, 7-9 March 2017
Published date:
5 March 2020
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...
Published date:
5 March 2020
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...
Published date:
4 March 2020
Nuclear materials science investigates how corrosion, irradiation, thermal ageing and mechanical load may affect materials properties and potentially degrade their performance.
Published date:
10 March 2020
NEA/NSC/R(2019)7
The modelling and simulation of nuclear systems allow scientists and engineers to probe aspects of the operation of these systems beyond what has been precisely measured. This has numerous applicatio...
Published date:
11 October 2022
Questions relating to the space, time end energy distribution of neutrons and radiation in different media are the domain of reactor physics.
Published date:
2 December 2019
Under the guidance of the Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM), the Expert Group on Fuel Materials (EGFM) focuses on materials science aspects of...
Published date:
3 March 2023
Under the guidance of the Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM), the Expert Group on Structural Materials (EGSM) focuses on materials science aspe...
Published date:
3 March 2023
NEA and NRA held joint conference on regulators' views in Tokyo, Japan 10 years after TEPCO Fukushima Daiichi NPS Accident.
Published date:
12 December 2022
Much has been learnt in the ten years since the Great Eastern Japan Earthquake and the subsequent accident at the Fukushima Daiichi Nuclear Power Plant, but significant challenges still remain.
This ...
Published date:
3 March 2021
High Burnup Experiments in Reactivity Initiated Accident (HERA) is dedicated to the understanding of LWR fuel performance at high burn-up under reactivity-initiated accidents (RIA).
Published date:
6 March 2023
8 -
12 May 2023
Krakow, Poland
The ENYGF is a biennial event that alternates with the International Youth Nuclear Congress (IYNC). The ENYGF’s objective is to provide a network for international communication and sharing knowledge...
Published date:
7 March 2023