This NEST project aims to integrate SMR research projects from the individual Participating Organisation countries into a broader and more impactful programme. It will include elements of technology ...
Published date:
18 February 2020
The NEA nuclear science programme is developed and executed by the Nuclear Science Committee (NSC), comprising high-level scientific experts from all NEA member countries.
Published date:
15 May 2023
Refined models for best-estimate calculations based on good-quality experimental data can improve the understanding of phenomena and the quantification of margins for operating nuclear power reactors...
Published date:
7 July 2006
This report provides the specification for the uncertainty exercises of the international OECD/NEA, NRC and NUPEC BFBT benchmark problem including the elemental task. The specification was prepared j...
Published date:
1 January 2010
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)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/DOC(2012)1
Based on the success of the OECD/NRC BFBT Benchmark, Japan released data based on the NUPEC PWR Sub-channel and Bundle Tests (PSBT) Benchmark and asked Pennsylvania State University (PSU) in the Unit...
Published date:
4 January 2012
NEA/NSC/DOC(2003)1
21-22 January 2003, Barcelona, Spain
Published date:
1 May 2003
Published date:
10 December 2000
NEA/NSC/DOC(2002)15
6 October 2002, Seoul, Korea
Published date:
1 November 2002
NEA/NSC/DOC(2001)20
Paul Scherrer Institute, Villigen, Switzerland, 15-16 October 2001
Published date:
1 October 2001
NEA/NSC/DOC(2002)11
Rossendorf (Dresden), Germany, 28-30 May 2002
Published date:
29 July 2002
NEA/NEACRP/L(1991)333
A summary of the Sixth Symposium on Reactor Noise (SMORN VI), Gatlinburg, United States, 19-24 May 1991
Published date:
1 January 1991
NEA/NSC/DOC(1996)17
Overview of the 7th Symposium on Reactor Surveillance and Diagnostics (SMORN-VII), 19-23 June 1995, Avignon, France
Published date:
1 January 1996
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
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...
Published date:
23 March 2022
For nuclear utility companies that opt to reprocess spent fuel, recycle it or do both, one of the main pertinent issues is plutonium recycling.
Published date:
8 September 2021
Attitudes towards plutonium management vary from country to country and from utility to utility: some regard plutonium as a liability and others as a valuable source of energy.
The purpose of this st...
Published date:
1 November 1995
The quality of the isotopic composition of plutonium fuel degrades as the number of recycles increases in thermal reactors. There are in addition incentives to better utilise fuel by increasing the b...
Published date:
19 July 1995
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...
Published date:
17 November 2020
Studies on fast reactors have historically concentrated on their capability of using plutonium produced in thermal reactors as initial fuel, and subsequently their capacity to produce electricity whi...
Published date:
1 November 1995
The NEA has studied multiple recycling issues associated with various reactor systems fuelled with mixed-oxide (MOX) and published a series of computational physics benchmarks. This has led to improv...
Published date:
21 June 2007
Studies on fast reactors have historically concentrated on their capability to use plutonium produced in thermal reactors as initial fuel, and subsequently their capacity to produce electricity while...
Published date:
1 November 1996
Although the recycling of plutonium as thermal mixed-oxide (MOX) fuel in pressurised water reactors (PWRs) is now well-established on a commercial scale, many physics questions remain. The main quest...
Published date:
23 October 2002
The commercial recycling of plutonium as PUO2/UO2 mixed-oxide (MOX) fuel is an established practice in pressurised water reactors (PWRs) in several countries, the main motivation being the consumptio...
Published date:
10 March 2003
The NEA has studied multiple recycling issues associated with various reactor systems fuelled with mixed-oxide (MOX) and published a series of computational physics benchmarks. This has led to improv...
Published date:
21 June 2007
The OECD/NEA Task Force on Computing Radiation Dose and Modelling of Radiation-Induced Degradation of Reactor Components (TFRDD) launched two international blind intercomparison exercises to examine ...
Published date:
1 January 2000
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...
Published date:
10 December 2020
Published date:
1 January 1974
Published date:
1 January 1977
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
Spent nuclear fuel contains minor actinides (MAs) such as neptunium, americium and curium, which require careful management. This becomes even more important when mixed oxide (MOX) fuel is being used...
Published date:
17 February 2015
A number of tests with detail well documented neutronics and thermal-hydraulics measurements data have been performed at the Rostov Unit 2 (Rostov-2) nuclear power plant (NPP). The reactor type is a ...
Published date:
2 August 2022
22 -
26 May 2023
NEA, Paris (France)
Place: OECD/NEA Headquarters in Paris, France
Minimum enrollment required: 12 participants
Course fee: 2300 EUR
Registration closed
The training course will be taught in English.
Participan...
Published date:
17 May 2023
NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 15-19 February 2021.
Published date:
24 February 2021
NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 19-21 February 2020.
Published date:
4 March 2020
NEA/NSC/R(2015)3
Twelfth Workshop Proceedings, Batavia, Illinois, United States, 28-30 April 2014
Published date:
2 June 2015
Published date:
8 December 2021
NEA/NSC/R(2021)2
Proceedings of the Fourteenth Workshop, 30 October-2 November 2018, Gyeongju, Korea.
Published date:
16 December 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...
Published date:
4 February 2021
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
28 -
29 April 2006
Pisa, Italy
Published date:
18 December 2020
NEA/NSC/DOC(1996)25
In this benchmark exercise the goal is to test the current state-of-the-art two-dimensional methods of calculating neutron flux to reactor components against the measured data of the VENUS-1 critical...
Published date:
1 January 1996
Average fuel burn-up in light water reactors (LWRs) has steadily increased with time as technological advances have been made. The practical limit is currently in the region of 50 GWd/t. The main dri...
Published date:
22 August 2006
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:
31 December 2003
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:
30 June 2006
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
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
The United States and the Russian Federation have each agreed to dispose of 34 tonnes of weapons-grade plutonium that are beyond their defence needs. One effective way to dispose of this plutonium is...
Published date:
20 January 2006
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...
Published date:
7 February 2023
