Published date:
1 January 1989
Published date:
1 January 2000
Published date:
20 June 2001
Published date:
21 June 2007
Published date:
19 November 2004
Published date:
19 November 2004
Published date:
19 November 2004
Published date:
13 July 2009
Published date:
16 December 2009
Published date:
5 June 2007
Uranium-235 Capture Cross-section in the keV to MeV Energy Region
Published date:
7 October 2011
Epithermal Capture Cross-Section of U-235
Published date:
1 January 1999
Nuclear Data for Improved LEU-LWR Reactivity Predictions
Published date:
29 November 2006
U-238 Capture and Inelastic Cross-Sections
Published date:
1 January 1999
Delayed Neutron Data for the Major Actinides
Published date:
11 October 2002
Current knowledge of the nuclear physics of fuels and materials provides an understanding and simulation of the operations of nuclear reactors and other systems, both under ordinary and exceptional c...
Published date:
18 July 2019
Evaluation Method of Inelastic Scattering Cross-sections for Weakly Absorbing Fission-product Nuclides
Published date:
21 September 2001
Cross-section Fluctuations and Self-shielding Effects in the Unresolved Resonance Region
Published date:
1 January 1996
Effects of Shape Differences in the Level Densities of Three Formalisms on Calculated Cross-Sections
Published date:
1 January 1998
Neutron Activation Cross-section Measurements from Threshold to 20 MeV for the Validation of Nuclear Models and Their Parameters (Volume 19)
Published date:
12 December 2005
Published date:
7 October 2011
Generation of Covariance Files for Iron-56 and Natural Iron
Published date:
1 January 1996
This document serves as a summary of the work of Subgroup 20 (SG20) on covariance matrix evaluation and processing in the resolved/unresolved resonance regions, organised under the auspices of the NE...
Published date:
18 August 2006
Covariance Data in the Fast Neutron Region
Published date:
7 October 2011
This publication reports the conclusions from the work undertaken by Subgroup 26 of the NEA Working Party on International Nuclear Data Evaluation Co-operation (WPEC), which focused on the developmen...
Published date:
1 September 2008
Published date:
20 December 2013
Processing and Validation of Intermediate Energy Evaluated Data Files
Published date:
28 December 2000
The following report has been issued by WPEC Subgroup 30, whose mission was to improve the accessibility and the quality of the EXFOR database to ensure that its invaluable contents can be used in co...
Published date:
7 October 2011
Subgroup 21 of the NEA Nuclear Science Committee Working Party on International Evaluation Co-operation was charged with the task of assessing neutron cross-section evaluations for fission products. ...
Published date:
8 July 2005
This publication reports the conclusions from the work undertaken by Subgroup 23 of the NEA Working Party on International Nuclear Data Evaluation Co-operation (WPEC), whose mission was to produce an...
Published date:
27 September 2009
This publication presents the conclusions of the work undertaken by Subgroup 25 of the NEA Working Party on International Evaluation Co-operation, which focused on the assessment and improvement of t...
Published date:
14 November 2007
A Working Party on International Evaluation Co-operation was established under the sponsorship of the OECD/NEA Nuclear Science Committee (NSC) to promote the exchange of information on nuclear data e...
Published date:
1 January 1996
Actinide Data in the Thermal Energy Range
Published date:
1 January 1996
Plutonium-239 Fission Cross-section Between 1 and 100 keV
Published date:
1 January 1996
Nuclear Models to 200 MeV for High-Energy Data Evaluations
Published date:
1 January 1998
Status of Pseudo-Fission-Product Cross-Sections for Fast Reactors
Published date:
1 January 1998
ICSBEP Guide to the Expression of Uncertainties
Published date:
24 March 2020
Source Convergence in Criticality Safety Analyses - Phase II: Guidance for Analysts
Published date:
24 March 2020
Published date:
16 May 2003
Published date:
16 May 2003
Published date:
9 September 2008
Published date:
20 December 2006
Published date:
21 February 2012
The NEA Working Party on Nuclear Criticality Safety established an Expert Group on Criticality Excursion Analysis in 2001 to explore the performance of various transient codes to evaluate criticality...
Published date:
17 July 2009
Published date:
7 April 2020
14 -
17 October 2019
Antwerp, Belgium
The Nuclear Energy Agency (NEA) organised the fourth international workshop on technology and components of accelerator driven systems (TCADS-4). The meeting was held in Antwerp, Belgium on 14-17 Oct...
Published date:
21 April 2020
by Robert J. Lemire (Chairman), Urs Berner, Claude Musikas, Donald A. Palmer, Peter Taylor and Osamu Tochiyama
This volume is the 13a in the OECD Nuclear Energy Agency (NEA) Chemical Thermodynamics s...
Published date:
13 December 2013
by Heinz Gamsjäger (Chairman), Tamás Gajda, James Sangster, Surendra K. Saxena, and Wolfgang Voigt
This volume is the 12th in the OECD Nuclear Energy Agency (NEA) Chemical Thermodynamics series. It i...
Published date:
31 December 2013
by Jordi Bruno (Chairman), Dirk Bosbach, Dmitrii Kulik and Alexandra Navrotsky
This volume provides a state-of-the-art report on the modelling of aqueous-solid solution systems by the combined use of...
Published date:
25 July 2007
by Robert J. Lemire (Chairman), Jean Fuger, Heino Nitsche, Paul Potter, Malcolm H. Rand, Jan Rydberg, Kastriot Spahiu, James C. Sullivan, William J. Ullman, Pierre Vitorge and Hans Wanner
This volume...
Published date:
6 June 2001
The present volume is a reprint of the 1992 edition of Chemical Thermodynamics of Uranium.
by Ingmar Grenthe (Chairman), Jean Fuger, Rudy J. M. Konings, Robert J. Lemire, Anthony B. Muller, Chinh N...
Published date:
2 June 2004
The present volume is a reprint of the 1995 edition of Chemical Thermodynamics of Americium.
by Robert J. Silva (Chairman), Giovanni Bidoglio, Malcolm H. Rand, Piotr B. Robouch, Hans Wanner and Ign...
Published date:
2 June 2004
Performance assessment of repository concepts for the geological disposal of long-lived radioactive waste relies on the availability of thermodynamic data for many radionuclides and other elements un...
Published date:
29 August 2002
Published date:
30 October 2015
Criticality is the state of a nuclear reactor when there is a self-sustaining chain reaction of fissionable material. Criticality experiments are controlled tests using fissile materials, like pluton...
Published date:
24 March 2020
Criticality is the state of a nuclear reactor when there is a self-sustaining chain reaction of fissionable material. Used or spent fuel criticality is associated with the scientific issues around as...
Published date:
24 March 2020
A criticality excursion (also referred to as a criticality accident) is the accidental production of a self-sustaining or divergent chain reaction of fissionable material.
Published date:
24 March 2020
Criticality is the state of a nuclear reactor when there is a self-sustaining chain reaction of fissionable material. Criticality safety analysis relates to evaluation approaches in data and computat...
Published date:
24 March 2020
JEF-2.2 Radioactive Decay Data; NEA Data Bank (August 1994).
Published date:
1 January 1994
Table of Simple Integral Neutron Cross Section Data from JEF-2.2, ENDF/B-VI, JENDL-3.2, BROND-2 and CENDL-2; NEA Data Bank (1994).
Published date:
1 January 1994
Published date:
5 August 2020
Knowledge of basic nuclear physics data is essential for the modelling and safe operation of all types of nuclear facilities. The de facto international standard format, Evaluated Nuclear Data File 6...
Published date:
25 September 2020
International Workshop on Nuclear Data Evaluation for Reactor Applications (WONDER)
Published date:
23 September 2020
U-Zr-O system miscibility gap in the liquid state. Source: Guéneau et al. Journal of Nuclear Materials 254 (1998), 158-174.
Published date:
5 May 2020
The fourth international NEA workshop on Technology and Components of Accelerator‑Driven Systems (TCADS‑4), 14‑17 October 2019.
Published date:
18 November 2019
by Malcom Rand (Chairman), Jean Fuger, Ingmar Grenthe, Volker Neck and Dhanpat Rai
This volume is the 11th in the OECD Nuclear Energy Agency (NEA) Chemical Thermodynamics series. It is based on a cri...
Published date:
22 January 2009
Published date:
5 May 2020
Published date:
1 January 1995
Published date:
1 January 1995
Published date:
1 January 1993
Published date:
1 January 1992
Published date:
1 January 1991
Published date:
1 January 1994
Published date:
1 January 1998
Published date:
1 January 1999
Published date:
1 January 1996
Published date:
1 January 1994
Published date:
1 January 1999
Published date:
1 January 1999
Published date:
1 January 1999
Published date:
1 January 1999
Published date:
1 January 1981
Published date:
1 January 1979
Published date:
1 January 1983
Published date:
1 January 1988
Published date:
1 January 1991
Published date:
1 January 1981
Published date:
1 January 1984
Published date:
1 January 1987
Published date:
1 January 1991
Published date:
1 January 2000
Published date:
14 February 2001
Published date:
25 October 2001
Published date:
4 February 2002
Published date:
30 August 2002
Published date:
9 May 2001
Published date:
11 January 2002
Published date:
22 May 2003
Published date:
11 August 2004
Published date:
20 October 2003
Published date:
19 July 2004
Published date:
26 October 2005
Published date:
20 July 2005
Published date:
27 October 2006
Published date:
18 December 2006
Published date:
26 June 2006
Published date:
3 April 2008
Published date:
29 October 2007
Published date:
9 May 2007
Published date:
25 May 2009
Published date:
20 February 2009
Published date:
28 June 2011
Published date:
1 June 2012
Materials research is a field of growing relevance for innovative nuclear systems, such as Generation IV reactors, critical and sub-critical transmutation systems and fusion devices. For these differ...
Published date:
31 December 2013
Structural materials research is a field of growing relevance in the nuclear sector, especially for the different innovative reactor systems being developed within the Generation IV International For...
Published date:
10 July 2008
State-of-the-Art Report on Multi-Scale Modelling Methods
Published date:
9 October 2020
NEA Working Party on International Nuclear Data Evaluation Co-operation (WPEC) 50th Subgroup (SG50), 14-15 September 2020.
Published date:
9 October 2020
NEA Nuclear Science Committee (NSC) meeting, 23-25 September 2020.
Published date:
9 October 2020
SFCOMPO 2.0 (Spent Fuel Isotopic Composition) is a relational database designed to facilitate the search and visualisation of experimental assay data of spent nuclear fuel.
Published date:
2 October 2020
Sensitivities Viewer is a Java based software which can read sensitivities files and plot sensitivities profiles.
Published date:
25 September 2020
Programme for Workshop on Increased Accident Tolerance of Fuels for LWRs, 10-12 December 2012
Published date:
25 February 2020
Ninth International Conference on Nuclear Criticality (ICNC2011) - Programme and call for papers
Published date:
6 March 2020
WPNCS 2019 meetings - Subgroup 2 (SG-2) agenda
Published date:
6 March 2020
WPNCS 2019 meetings - Subgroup 3 (SG-3) agenda
Published date:
6 March 2020
WPNCS 2019 meetings - Subgroup 4 (SG-4) agenda
Published date:
6 March 2020
WPNCS 2019 meetings - Subgroup 1 (SG-1) agenda
Published date:
6 March 2020
WPNCS 2019 meetings - Subgroup 6 (SG-6) agenda
Published date:
6 March 2020
WPNCS 2019 meetings - Subgroup 5 (SG-5) agenda
Published date:
6 March 2020
WPNCS 2019 meetings - WPNCS agenda
Published date:
6 March 2020
WPNCS 2019 meetings - Subgroup 7 (SG-7) agenda
Published date:
6 March 2020
Published date:
12 March 2020
Published date:
12 March 2020
Published date:
12 March 2020
Published date:
12 March 2020
Published date:
12 March 2020
Published date:
12 March 2020
Published date:
12 March 2020
Published date:
12 March 2020
Published date:
12 March 2020
Published date:
12 March 2020
Published date:
12 March 2020
Published date:
12 March 2020
Published date:
12 March 2020
Published date:
12 March 2020
Published date:
12 March 2020
Published date:
12 March 2020
Thermal Scattering Law S(α,β): Measurement, Evaluation and Application
Published date:
13 March 2020
Published date:
23 March 2020
Nuclear data thermal scattering
Published date:
9 March 2020
Fourth International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-4) – Programme
Published date:
3 March 2020
Third International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-3) – Programme
Published date:
3 March 2020
19 -
22 September 2011
Edinburgh, Scotland
The Ninth International Conference on Nuclear Criticality Safety (ICNC2011) was held on from 19-22 September 2011 in Edinburgh, Scotland. ICNC 2011 allowed specialists from around the globe to come t...
Published date:
6 March 2020
14 May 2018
OECD Conference Centre, Paris, France
Published date:
12 March 2020
22 May 2019
ND2019, China National Convention Center, Beijing, China
Published date:
12 March 2020
26 June 2019
NEA Headquarters, Boulogne-Billancourt, France
Published date:
12 March 2020
24 June 2019
NEA Headquarters, Boulogne-Billancourt, France
Published date:
12 March 2020
7 -
10 October 2013
Idaho National Laboratory, Idaho Falls, United States
The OECD Nuclear Energy Agency (NEA) organised the Third International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-3). The workshop was held in Idaho Falls, USA on 7-10 Oct...
Published date:
3 March 2020
31 August 2010 -
3 September 2010
Daejeon, Republic of Korea
The Nuclear Energy Agency (NEA) is organising the Second International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-2). The workshop was held in Daejeon, Republic of Korea, ...
Published date:
5 March 2020
4 -
6 June 2007
Karlsruhe, Germany
Materials research is a field of growing relevance for innovative nuclear systems, such as Generation IV reactors, critical and sub-critical transmutation systems and fusion devices. For these differ...
Published date:
5 March 2020
Nuclear data covariance and assimilation
Published date:
9 March 2020
Nuclear data fission physics
Published date:
9 March 2020
Nuclear data measurements
Published date:
9 March 2020
Published date:
9 March 2020
Published date:
10 March 2020
NEA work in nuclear data formats
Published date:
9 March 2020
Nuclear data applications, verification and validation
Published date:
9 March 2020
The Collaborative International Evaluated Library Organisation (CIELO) Pilot Project, working under the auspices of the WPEC Subgroup 40 (SG40), was established to generate complete evaluations for a...
Published date:
10 March 2020
Co-ordinated Evaluation of Plutonium-239 in the Resonance Region
Published date:
12 March 2020
The Nuclear Energy Agency's High Priority Nuclear Data Request List (HPRL) is a compilation of the highest priority nuclear data requirements.
Published date:
4 December 2019
This volume is the 13b in the OECD Nuclear Energy Agency (NEA) Chemical Thermodynamics series. It is the second part of a critical review of the thermodynamic properties of iron, its solid compounds ...
Published date:
3 March 2020
Meeting Nuclear Data Needs for Advanced Reactor Systems
Published date:
13 March 2014
The ICSBEP Technical Review Group of over 65 international technical experts met remotely for the first time on 19-23 October 2020.
Published date:
4 November 2020
The decision to re-use plutonium generated in thermal reactors is a strategic one for a utility, and is closely tied to the spent fuel management strategy. One option is to reprocess the spent fuel i...
Published date:
3 November 2003
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 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 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
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
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:
21 December 2006
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
Published date:
24 November 2020
First Information Exchange Meeting on the Nuclear Production of Hydrogen, Paris, France, 2-3 October, 2000 - Programme and abstracts
Published date:
24 November 2020
Fourth Information Exchange Meeting on thr Nuclear Production of Hydrogen, 13-16 April 2009, Oakbrook, IL, USA - Programme
Published date:
24 November 2020
14 -
16 April 2009
Chicago, Illinois, United States
The NEA Nuclear Science Committee (NSC) had previously organised three information exchange meetings to discuss scientific and strategic matters pertaining to the nuclear production of hydrogen. Earl...
Published date:
14 April 2009
5 -
7 October 2005
Japan Atomic Energy Agency, Oarai, Japan
The NEA Nuclear Science Committee (NSC) had organised two previous information exchange meetings on the nuclear production of hydrogen. The last of these meetings was held in October 2003, where deve...
Published date:
5 October 2005
2 -
3 October 2003
Argonne National Laboratory, Illinois, USA
As growing demand for energy has prompted ever-increasing use of fossil fuels, the resulting issues of energy security and climate change have in turn led to renewed interest in the use of hydrogen a...
Published date:
2 October 2003
The page describes the NEA's work on computing radiation dose and modelling of radiation-induced degradation of reactor components.
Published date:
30 September 2020
Under the guidance of the Working Party on Scientific Issues of Reactor Systems (WPRS), the expert group performed specific tasks associated with radiation transport and shielding aspects of current ...
Published date:
3 March 2020
In response to growing interest in high-temperature, gas-cooled reactors (HTGRs) in many countries and the need for improved materials for nuclear applications in high-temperature environments, the N...
Published date:
1 June 2004
In response to increasing interest in high-temperature, gas-cooled reactors (HTGRs) in many countries and the need for improved materials for nuclear applications in high-temperature environments, th...
Published date:
29 May 2002
In response to increasing interest in high-temperature, gas-cooled reactors (HTGRs) and the need for improved knowledge of materials for nuclear applications that resist high temperatures, the NEA or...
Published date:
1 January 2000
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
The nuclear fuel cycle is the chain of processes whereby nuclear fuel is prepared and managed before and after its use in a reactor.
Published date:
2 December 2019
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
Historically, average discharge burn-ups in light water reactors (LWRs) have steadily increased with time as experience has accumulated and technological developments have progressed. The main benefi...
Published date:
30 September 2020
The Nuclear Science Committee (NSC), through its expert group, conducted a study on research and development (R&D) needs in nuclear science, held a workshop on R&D needs for current and future nuclea...
Published date:
30 September 2020
Published date:
1 January 1974
Published date:
1 January 1977
Radiation shielding is a protective shield that is inserted betweeen a source of ionising radiation and the object to protect to reduce the amount of damage that can happen to delicate or biological ...
Published date:
16 October 2020
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...
Published date:
16 December 2020
This publication provides an introduction to minor actinide nuclear properties and discusses some of the arguments in favour of minor actinide recycling, as well as the potential role of thermal reac...
Published date:
18 November 2013
Under the guidance of the Nuclear Science Committee (NSC) and under the mandate of the Working Party on Multi-scale Modelling of Fuels and Structural Materials for Nuclear Systems (WPMM), the objecti...
Published date:
5 March 2020
The Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of Light Water Reactors (LWRs) is an international high-visibility benchmark for unce...
Published date:
30 September 2020
This benchmark is based on a well-defined problem concerning a pressurised water reactor (PWR) main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the...
Published date:
19 November 2003
The benchmark is based on a well-defined problem concerning a PWR main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the main steam isolation valves....
Published date:
22 December 2000
This benchmark is based on a well-defined problem concerning a pressurised water reactor (PWR) main steam line break, which may occur as a consequence of the rupture of one steam line upstream of the...
Published date:
22 November 2002
Conditions for release, rules and restrictions applying to the Kalinin Unit 3 (Kalinin-3) Transient Benchmark caused by the switching-off of one of the four operating main circulation pumps (MCPs) at...
Published date:
30 September 2020
28 -
29 April 2006
Pisa, Italy
Published date:
18 December 2020
1 -
3 June 2016
Villigen, Switzerland
Published date:
18 December 2020
29 April 2009 -
1 May 2009
University Park/State College, Pennsylvania, United States
Published date:
18 December 2020
13 -
17 May 2019
Oak Ridge, United States
Published date:
18 December 2020
16 -
17 May 2018
Lucca, Italy
Published date:
18 December 2020
10 -
12 May 2017
Erlangen, Germany
Published date:
18 December 2020
20 -
22 May 2015
Madrid, Spain
Published date:
18 December 2020
9 -
11 May 2012
Karlsruhe, Germany
Published date:
18 December 2020
13 -
15 April 2011
Stockholm, Sweden
Published date:
18 December 2020
13 -
15 April 2010
Pisa, Italy
Published date:
18 December 2020
2 -
4 April 2008
Garching, Germany
Published date:
18 December 2020
10 -
11 May 2007
Paris, France
Published date:
18 December 2020
14 -
16 May 2014
Garching, Germany
Published date:
21 December 2020
3-D Radiation Transport benchmarks dealt with scientific issues in the field of deterministic and stochastic methods and computer codes relative to three dimensional (3-D) radiation transport.
Published date:
30 September 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...
Published date:
9 March 2020
IRPhE Handbook 2019 Edition - Contents
Published date:
30 September 2020
Published date:
1 February 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
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...
Published date:
5 March 2021
Published date:
21 June 2016
MeshTal Viewer is a Java based software which can read mesh tallies output formats of several neutron transport codes and display them graphically.
Published date:
2 October 2020
The Technical Review Group (TRG) for the International Assay Data of Spent Nuclear Fuel Database (SFCOMPO) lies under the direction of the Working Party on Nuclear Criticality Safety (WPNCS).
Published date:
13 April 2021
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.
Published date:
14 June 2021
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...
Published date:
26 July 2021
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
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 (...
Published date:
20 September 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...
Published date:
27 October 2021
20 -
23 September 2022
Facility for Rare Isotope Beams at Michigan State University, East Lansing, Michigan (USA)
The 15th workshop on Shielding aspects of Accelerators, Targets, and Irradiation Facilities (SATIF) is tentatively planned to be held in East Lansing, Michigan, USA, on 20-23 September 2022. The SATI...
Published date:
2 November 2021
The NEA Expert Group on Innovative Structural Materials (EGISM) organised a workshop on 19-21 October 2021 together with the Spanish Center for Energy, Environmental and Technological Research (CIEMA...
Published date:
3 November 2021
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...
Published date:
19 November 2021
The expert group dealt with the activities associated with the certification of experimental data and benchmark models along with establishing the processes and procedures for using the data and benc...
Published date:
23 November 2021
New NEA reports on nuclear data evaluation
Published date:
5 August 2020
Nuclear data refers to the probabilities, statistics and measurements of the physical interactions associated with atomic particles.
Published date:
16 December 2019
NEA Working Party on Scientific Issues of Reactor Systems (WPRS) workshops, 7-15 December 2020.
Published date:
17 December 2020
New NEA task force on partitioning and transmutation kicks off
Published date:
27 January 2021
NEA Thermodynamics of Advanced Fuels International Database updates
Published date:
25 January 2021
Preparatory meeting for Thermodynamic Characterisation of Fuel Debris and Fission Products Based on Scenario Analysis of Severe Accident Progression at Fukushima Daiichi Nuclear Power Station (TCOFF)...
Published date:
27 May 2021
Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) meeting, 8 June 2021.
Published date:
30 June 2021
The webinar "Research and international dialogue in technology nuclear power - What role for Italy?", was held on 17- 18 November 2021.
Published date:
14 December 2021
21 -
25 February 2022
ZOOM virtual meeting
Published date:
7 February 2022
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...
Published date:
17 March 2022
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
Collected sources of primary documentation for reactor physics benchmarks.
Published date:
14 April 2022
The International Criticality Safety Benchmark Evaluation Project (ICSBEP) released the first version of the Database for the International Handbook of Evaluated Criticality Safety Benchmark Experime...
Published date:
25 April 2022
Nuclear Data Sensitivity Tool (NDaST), aims to provide rapid feedback on the effect of changes to nuclear data on integral benchmarks.
Published date:
17 May 2022
27 June 2022 -
1 July 2022
OECD headquarters, Paris XVI
Published date:
1 June 2022
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...
Published date:
22 June 2022
30 May 2022 -
3 June 2022
Conference Center Hotel Aquabella, Aix-en-Provence, France (in-person meeting)
Published date:
29 March 2022
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...
Published date:
19 July 2022
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...
Published date:
19 July 2022
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...
Published date:
19 July 2022
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...
Published date:
19 July 2022
Multi-physics Pellet Cladding Mechanical Interaction Validation (MPCMIV) Benchmark
Published date:
19 July 2022
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 ...
Published date:
19 July 2022
TVA Watts Bar Unit 1 Multi-Physics Benchmark
Published date:
19 July 2022
The NEA Data Bank organised a PENELOPE training course at the University of Barcelona in Spain on 11-15 July 2022
Published date:
1 August 2022
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...
Published date:
2 August 2022
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
NUPEC Boiling Water Reactor (BWR) Full-size Fine-mesh Bundle Test (BFBT) Benchmark
Published date:
2 August 2022
Forsmark 1 and 2 Boiling Water Reactor Stability Benchmark
Published date:
2 August 2022
This benchmark incorporated full 3-D modelling of the reactor core into system transient codes for best-estimate simulations of the interactions between reactor core behaviour and plant dynamics and ...
Published date:
2 August 2022
An approach similar to the OECD/NRC Boiling Water Reactor Full-size Fine-mesh Bundle Tests (BFBT) Benchmark was adopted by dividing the benchmark activity into phases.
Published date:
2 August 2022
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 international benchmark concerned pebble bed modular reactor (PBMR) coupled neutronics/thermal-hydraulics transients based on the PBMR-400MW design.
Published date:
26 July 2021
The main objectives of this expert group are to assess the limitations of the NRT-dpa standard, in the light of both atomistic simulations and known experimental discrepancies; and to revisit the NRT...
Published date:
5 March 2020
The objectives of the expert group are to assess the accuracy and calculation time of the various first principle tools applied in the assessment of the properties of the nuclear materials; assess th...
Published date:
5 March 2020
The expert group was established to develop a nuclear data structure definition that can meet the needs of a broad set of nuclear data users and providers.
Published date:
20 September 2022
The expert group is responsible for managing the activities related to the High Priority Request List (HPRL) for nuclear data, in particular for guaranteeing that the entries are up-to-date and well-...
Published date:
20 September 2022
WPNCS bi-annual event brought together 80 experts from 17 member countries.
Published date:
7 February 2022
The NEA Data Bank Nuclear Data Service (NDS) organised the Joint Evaluated Fission and Fusion (JEFF) Nuclear Data Week (NDW) on 25-29 April 2022.
Published date:
20 May 2022
Recent meetings of groups working under the aegis of the Framework for Irradiation Experiments (FIDES) have demonstrated that the international community is enthusiastic and on a strong course to ful...
Published date:
5 May 2022
The NEA Data Bank's first in-person course since the pandemic started was on FISPACT, an enhanced multi-physics platform for neutron, proton, alpha, deuteron or gamma particle interactions.
Published date:
27 June 2022
Over its 25 years of existence, the working party has contributed many topics and has led advances in criticality safety studies.
Published date:
28 July 2022
The first QUENCH-ATF joint project test was successfully completed by the KIT team on 17 July 2022.
Published date:
5 August 2022
WPRS gathered 172 experts from 22 countries at the annual Benchmark Workshop.
Published date:
9 June 2022
The event gathered 129 participants from 75 international institutions.
Published date:
6 October 2022
As governments around the world are committing to reaching net zero emissions by 2050, many countries are looking at the role hydrogen can play in mitigating climate change. This page provides more i...
Published date:
16 September 2022
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 ...
Published date:
9 November 2022
The primary purpose of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) is to compile critical and subcritical benchmark experiment data into a standardised format that allo...
Published date:
10 November 2022
The International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at...
Published date:
10 November 2022
The 2021 edition can be downloaded online.
Published date:
22 November 2022
JANIS (Java-based nuclear information software) is an application designed to facilitate the visualisation and manipulation of nuclear data. JANIS will be helpful to engineers and physicists who use ...
Published date:
24 November 2022
MeshTal Viewer user manual
Published date:
25 November 2022
PWR MOX/UO2 Core Transient Benchmark
Published date:
7 December 2022
The 2021 edition contains data from 169 experimental series that were performed at 57 nuclear facilities.
Published date:
13 December 2022
Courses were held in November 2022 in paris, France.
Published date:
14 December 2022
Published date:
17 January 2023
The expert group primarily acted as a forum for scientific and technical information exchange on advanced light water reactor (LWR) fuels with enhanced accident tolerance.
Published date:
18 October 2022
20 -
24 February 2023
NEA headquarters (46, quai Alphonse Le Gallo, 92100 Boulogne-Billancourt, France) with a remote access option
Published date:
30 January 2023
Multiphysics are simulations using computer applications or software to couple multiple physical events in order to predict or validate the physical real-world outcome.
Published date:
16 October 2020
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1 January 1992
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1 January 1996
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1 January 1994
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1 January 1992
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1 January 1995
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1 January 1994
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1 January 1997
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1 January 1997
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1 January 1998
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1 January 1998
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1 January 2000
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8 December 2000
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22 December 2000
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21 February 2002
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7 July 2006
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27 September 2002
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8 August 2003
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1 January 1999
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1 January 1999
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18 April 2006
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31 December 2004
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29 July 2005
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28 April 2005
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9 July 2004
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25 June 2004
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29 December 2006
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15 December 2004
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7 July 2005
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29 December 2006
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19 May 2006
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7 February 2006
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9 October 2009
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17 November 2009
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29 September 2011
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12 May 2010
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31 December 2013
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29 July 2015
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10 September 2015
Materials performance is critical to the safe and economic operation of any nuclear system. As the international community pursues the development of Generation IV reactor concepts and accelerator-dr...
Published date:
21 October 2013
Development of innovative fuels such as homogeneous and heterogeneous fuels, ADS fuels, and oxide, metal, nitride and carbide fuels is an important stage in the implementation process of advanced nuc...
Published date:
12 December 2014
Future fuel cycle characteristics, feasibility and acceptability will be crucial for the continued development of nuclear energy, especially in the post-Fukushima context. Fuel cycle choices have bot...
Published date:
18 July 2013
Regional strategies can provide a useful framework for implementing innovative nuclear fuel cycles. The appropriate sharing of efforts and facilities among different countries is necessary in today’s...
Published date:
27 September 2009
Future nuclear fuel cycles could effectively address radioactive waste issues with the implementation of partitioning and transmutation (P&T). Previous studies have defined the infrastructure require...
Published date:
3 February 2009
Many countries have been performing a wide range of research on the partitioning and transmutation (P&T) of minor actinides and fission products. The aim is to provide greater flexibility in terms of...
Published date:
10 March 2010
As part of the development of advanced nuclear systems, including accelerator-driven systems (ADS) proposed for high-level radioactive waste transmutation and generation IV reactors, heavy liquid met...
Published date:
31 May 2007
Subgroup 7 of the NEA Working Party on International Nuclear Data Co-operation (WPEC) was established to re-evaluate the nuclear data standards cross-section. These cross-section data are the basis f...
Published date:
29 November 2006
This report has been prepared by Subgroup 9 which was set up in 1998 with the aim of investigating discrepancies found between microscopic and macroscopic data for the uranium-235 fission neutron spe...
Published date:
15 July 2003
Present Status of Minor Actinide Data
Published date:
1 January 1999
Published date:
1 January 1998
The NEA Working Party on Nuclear Criticality Safety (WPNCS) established an Expert Group on Source Convergence in Criticality Safety Analysis (EGSCCSA) to explore the problems of slow convergence and ...
Published date:
11 September 2006
NEA/NSC/DOC(1996)6
Isotopic Prediction: Final Report, M.D. DeHart (ORNL), M.C. Brady (SNL), C.V. Parks (ORNL). Publication date June 1996. ORNL-6901
Published date:
1 January 1996
NEA/NSC/DOC(1996)1
JAERI-Research 96-003, M. Takano, H. Okuno, (JAERI), publication date: February 1996
Published date:
1 January 1996
NEA/NSC/DOC(1998)1
Results - Conceptual PWR Spent Fuel Transportation Cask, A. Nouri
Published date:
1 January 1998
NEA/NSC/R(2015)1
Impact of Isotopic Inventory Changes due to Control Rod Insertions on Reactivity and the End Effect in PWR UO2 Fuel Assemblies
Published date:
2 June 2015
NEA/NSC/R(2015)6
Nuclide Composition and Neutron Multiplication Factor of a Boiling Water Reactor Spent Fuel Assembly for Burn-up Credit and Criticality Control of Damaged Nuclear Fuel
Published date:
2 October 2015
NEA/NSC/DOC(1992)10
Isotopic Prediction (Problem Specification). Revised, January 1993 Michaele C. Brady<br>See <a href="/html/science/docs/1996/nsc-doc96-06.pdf">NEA/NSC/DOC(96)6</a>.
Published date:
1 January 1992
NEA/NSC/DOC(1993)15
Effect of Axial Burnup Profile (Infinite fuel pin array) Makoto Takano (JAERI), Michaele Brady (SNL), Alain Santamarina (CEA), June 1993. See NEA/NSC/DOC(96)1
Published date:
1 January 1993
NEA/NEACRP/L(1991)337
Simple PWR Spent Fuel Cell (Problem Specification), Makoto TAKANO (JAERI), Michaele BRADY (ORNL), 1991
Published date:
1 January 1991
NEA/NSC/DOC(1997)11
Hiroshi OKUNO, Yoshitaka NAITO and Yoshihira ANDO (JAERI)
Published date:
1 January 1997
NEA/NSC/DOC(2000)12
Criticality Calculations of BWR Spent Fuel in Storage and Transport, Hiroshi OKUNO, Yoshitaka NAITO, Yoshihira ANDO
Published date:
30 June 2000
NEA/NSC/DOC(2002)2
Burn-up Calculations of BWR Fuel Assemblies for Storage and Transport
Published date:
16 January 2002
NEA/NSC/DOC(1993)22
JAERI-M-94-003 Makoto TAKANO (JAERI), January 1994
Published date:
1 January 1993
NEA/NSC/R(2016)2
Numerical benchmark for the analysis of small-sample reactivity experiments
Published date:
9 June 2016
NEA/NSC/DOC(2003)4
Results and Analysis of MOX Fuels Depletion Calculations
Published date:
17 April 2003
NEA/NSC/DOC(2003)3
Reactivity Prediction Calculations for Infinite Arrays of PWR Mox Fuel Pincells
Published date:
17 April 2003
NEA/NSC/DOC(1996)4
Criticality Calculations of BWR Spent Fuel in Storage and Transportation, Yoshitaka Naito, Hiroshi Okuno and Yoshihara Ando (JAERI)
Published date:
1 January 1996
NEA/NSC/DOC(1995)3
Document content and format guide for the International Criticality Safety Benchmark Evaluation Project (ICSBEP) – NEA/NSC/DOC(95)03
Published date:
24 March 2020
Published date:
12 December 2018
The implementation of advanced nuclear systems requires that new technologies associated with the back end of the fuel cycle are developed. The separation of minor actinides from other fuel component...
Published date:
19 March 2018
Preservation of know-how in the nuclear field is promoted through the activities of the OECD Nuclear Energy Agency Data Bank. One area of importance concerns methods for solving radiation transport p...
Published date:
1 September 2008
NEA/NSC/R(2018)1
LACANES – Phase II: Natural Convection
Published date:
4 April 2018
Published date:
2 December 2016
NEA/NSC/R(2015)5
State-of-the-Art Report on Multi-scale Modelling of Nuclear Fuels
Published date:
3 September 2015
NEA/NSC/DOC(2015)9
Primary Radiation Damage in Materials – Review of Current Understanding and Proposed New Standard Displacement Damage Model to Incorporate in Cascade Defect Production Efficiency and Mixing Effects
Published date:
26 February 2015
NEA/NSC/WPFC/DOC(2012)17
LACANES – Phase I: Isothermal forced convection case
Published date:
12 June 2012
Published date:
12 June 2012
NEA/NSC/WPFC/DOC(2012)15
Spent Nuclear Fuel Reprocessing Flowsheet
Published date:
12 June 2012
Published date:
4 January 2012
As part of a broader spectrum of collaborative activities underpinning nuclear materials research, the Nuclear Energy Agency is supporting worldwide efforts towards the development of advanced materi...
Published date:
28 September 2018
NEA/NSC/R(2020)2
The present report provides a summary of the experiments analysed and consensuses reached by NEA WPEC Subgroup 41, including final recommendations based on all experimental data available at the time...
Published date:
28 September 2020
NEA/NSC/R(2020)3
The following report is issued by WPEC Subgroup 28, which builds upon the work of the previous Subgroup 20 for developing new methods for cross-section covariance evaluation. Subgroup 28 was tasked w...
Published date:
28 September 2020
NEA News is the professional journal of the Nuclear Energy Agency (NEA). It features articles on the latest nuclear energy issues concerning the economic and technical aspects of nuclear energy, nucl...
Published date:
29 June 2004
NEA/NSC/WPNCS/DOC(2011)5
Spent Nuclear Fuel Assay Data for Isotopic Validation - State-of-the-art Report
Published date:
6 June 2011
NEA/NSC/DOC(2013)9
Workshop Proceedings, 10-12 December 2012
Published date:
25 February 2020
In order to validate the calculations methods and nuclear data used for the prediction of power in MOX-fuelled systems, the OECD Nuclear Energy Agency (NEA) has examined a series of theoretical physi...
Published date:
9 February 2004
An important issue regarding deterministic transport methods for whole core calculations is that homogenised techniques can introduce errors into results. In addition, with modern computational abili...
Published date:
16 September 2005
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:
8 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:
20 July 2001
Published date:
10 December 2000
NEA/NSC/DOC(2001)20
Paul Scherrer Institute, Villigen, Switzerland, 15-16 October 2001
Published date:
1 October 2001
NEA/NSC/DOC(2003)1
21-22 January 2003, Barcelona, Spain
Published date:
1 May 2003
NEA/NSC/DOC(2002)15
6 October 2002, Seoul, Korea
Published date:
1 November 2002
NEA/NSC/DOC(2002)11
Rossendorf (Dresden), Germany, 28-30 May 2002
Published date:
29 July 2002
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:
7 July 2005
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 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
It is essential to calculate the structural integrity of reactor components with a high degree of accuracy in order to make correct decisions regarding plant lifetime at the design stage, safety marg...
Published date:
11 April 2006
NEA/NSC/DOC(1996)5
The OECD/NEA Nuclear Science Committee Task Force on Computing Radiation Dose and Modelling of Radiation-induced Degradation of Reactor Components was set up in November 1995 in response to a request...
Published date:
1 January 1996
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
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
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
NEA/NSC/DOC(2000)4
Several NEA Nuclear Science Committee (NSC) activities are concerned with the validation of computation methods and codes as applied to nuclear technology. One of the challenges has been and continue...
Published date:
17 March 2000
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
Since the beginning of benchmark activities, two benchmark workshops took place. The first was held in Madrid, Spain (June 1998), and the second in Garching near Munich, Germany (March 1999). It was ...
Published date:
1 January 1999
NEA/NSC/DOC(2007)1/1
Particle transport calculations in three-dimensional configurations are becoming prevalent in nuclear applications. This places a premium on determining the accuracy of numerical solutions to practic...
Published date:
23 February 2007
NEA/NSC/DOC(2009)8
Saratoga Springs, New York, 6 May 2009 - Meeting summary
Published date:
11 May 2009
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
NEA/NSC/R(2020)8
The following report is issued by the WPEC Subgroup 27, which builds upon the work of the previous Subgroups 21 and 23, critically reviewing the gamma emission data and providing recommendations to i...
Published date:
1 February 2022
Published date:
10 November 2016
One of the important issues regarding deterministic transport methods for whole core calculations is that homogenised techniques can introduce errors into results. On the other hand, with modern comp...
Published date:
8 August 2003
Hydrogen has the potential to play an important role as a sustainable and environmentally acceptable energy source in the 21st century. However, hydrogen does not exist as a gas on earth and thus has...
Published date:
5 June 2001
Hydrogen has the potential to play an important role as a sustainable and environmentally acceptable energy carrier in the 21st century. Since natural sources of pure hydrogen are extremely limited, ...
Published date:
13 July 2006
Hydrogen has the potential to play an important role as a sustainable and environmentally acceptable source of energy in the 21st century. Present methods for producing hydrogen are mainly based on t...
Published date:
28 April 2004
NEA/NSC/R(2020)4
Advanced nuclear fuel cycles to improve the safety, sustainability and economics of nuclear energy are being investigated worldwide. Partitioning and transmutation (P&T) is one of the candidate techn...
Published date:
11 October 2022
Particle accelerators have evolved over the last decades from simple devices to powerful machines, and are having an increasingly important impact on research, technology and daily life. Today they h...
Published date:
8 October 2013
Particle accelerators have evolved over the last decades from simple devices to powerful machines, and are having an increasingly important impact on research, technology and daily life. Today they c...
Published date:
15 December 2010
Particle accelerators are used today for an increasing range of scientific and technological applications. They are very powerful tools to investigate the origin and structure of matter, and to impro...
Published date:
13 May 2005
Particle accelerators are used today for an increasing range of scientific and technological applications. They are very powerful tools for investigating the origin and structure of matter, and for i...
Published date:
22 July 2004
Over the last 50 years particle accelerators have evolved from simple devices to powerful machines, and will continue to have an important impact on research, technology and lifestyle. Today, they co...
Published date:
30 May 2001
Over the last 50 years particle accelerators have evolved from simple devices to powerful machines, and will continue to have an important impact on research, technology and lifestyle. Today, they co...
Published date:
1 January 1999
Particle accelerators have evolved over the last 50 years from simple devices to powerful machines, and will continued to have an important impact on research, technology and lifestyle. Today, they c...
Published date:
1 January 1998
This Strategic Plan is intended to guide the NEA as it seeks to meet the evolving needs of member countries in the application and exploration of nuclear science and technology. The plan includes an ...
Published date:
22 December 2016
The OECD Nuclear Energy Agency (NEA) Strategic Plan serves as a guiding instrument that reflects the priorities of its member countries as the Agency addresses evolving needs in the exploration and a...
Published date:
25 January 2022
NEA/NSC/R(2022)4
Under the auspices of the NEA Nuclear Science Committee (NSC), the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) was established to co-ordinate scientific activities related to ad...
Published date:
29 November 2022
NEA/NSC/R(2021)1
This benchmark report has been compiled under the guidance of the NEA Working Party on Nuclear Criticality Safety (WPNCS) in the Subgroup on the Role of Integral Experiment Uncertainties and Covarian...
Published date:
30 January 2023
NEA/NSC/R(2021)4
The understanding of nuclear physics and the associated uncertainties is essential to the modelling of all nuclear systems. Nuclear reaction probabilities, emitted particle energies and angles, fissi...
Published date:
8 February 2023
The brochure provides background information about the NEA.
Published date:
10 September 2018
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
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
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
Published date:
16 May 2013
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(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
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
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
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
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
This benchmark is organised to examine the models for fission gas release during anticipated operational occurrences (AOOs).
Published date:
7 March 2023
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...
Published date:
8 March 2023
3 -
5 September 2019
OECD Conference Centre, CC15, 2 rue André Pascal, 75016, Paris, France
The continued evolution of fuel and materials technology, fuel performance, optimisation of operational limits, material ageing, failure limits, etc. requires experimental evidence obtained from test...
Published date:
27 February 2020
EGPRS Task Force members met on 3 April 2023.
Published date:
7 April 2023
NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 15-19 February 2021.
Published date:
24 February 2021
ICSBEP, SINBAD AND IRPhEP Technical Review Group meetings, October 2021.
Published date:
25 October 2021
NEA Working Party on Scientific Issues of Reactor Systems (WPRS) annual meeting, 19-21 February 2020.
Published date:
4 March 2020
ICSBEP, SINBAD AND IRPhEP Technical Review Group meetings
Published date:
18 November 2019
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...
Published date:
12 April 2023
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...
Published date:
25 April 2023
International experts gathered at the NEA for the commencement of the third phase TAF-ID on 16-17 February 2023.
Published date:
24 February 2023
Thermodynamic databases and accident prevention
Published date:
24 February 2023
Expert groups on structural and fuel materials meet to advance materials science activities
Published date:
24 February 2023
The WPRS met from 20-24 February 2023.
Published date:
17 March 2023
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.
Published date:
21 April 2023
The Technical Review Groups for both projects met at the NEA headquarters on 3-7 April 2023.
Published date:
24 April 2023
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6 June 2023
Oregon State University, Corvallis, Oregon, United States
Published date:
20 April 2023
NEA/NSC/R(2021)5
Since the early 2000s there is an increasing demand from nuclear research, industry, safety and regulation for best-estimate predictions to be provided with their confidence bounds. Consequently, an ...
Published date:
18 April 2023
NEA/NSC/R(2021)3
Monte Carlo criticality calculations involve a two-step procedure based on a stochastic implementation of the power iteration method: first, achieve convergence of the fission source distribution dur...
Published date:
17 February 2023
NEA/NSC/R(2022)5
This report presents the results of a benchmark study on innovative fuels for fast reactors using fuel performance codes. Irradiation results were shared among participants of the expert group and co...
Published date:
3 April 2023
22 -
26 May 2023
Zanhotel Europa, Via Cesare Boldini 11, Bologna, Italy + virtual option on ZOOM
Published date:
17 May 2023
Sustained performance of nuclear technology depends on access to a talented and well-qualified workforce, thus it is important to ensure that adequate infrastructures exist for education and training...
Published date:
22 July 2020
Under the guidance of the Nuclear Science Committee (NSC), the Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM) addresses materials science aspects of nuclea...
Published date:
1 June 2023
Lead-cooled Fast Reactors (LFR) are rather new concepts which have gathered increasing international attention after the Generation-IV International Forum (GIF) selected them as promising candidates ...
Published date:
9 June 2023
The FIDES-II framework is designed to do more than just produce data on transient fuel behavior and safety related issues.
Published date:
13 June 2023
WPFM held meetings on 23-25 May 2023.
Published date:
13 June 2023
The first International School on Simulation of Nuclear Reactor Systems (SINUS) took place on 22-23 May 2023.
Published date:
14 June 2023
Kick-off workshop of the thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using High Temperature Test Facility (HTTF) data.
Published date:
16 June 2023
10-year FIDES-II strategic plan will define key research needs in a variety of technical disciplines.
Published date:
19 June 2023
The annual WPRS Benchmarks Workshops took place on 22-26 May 2023 in Bologna, Italy.
Published date:
13 June 2023
Published date:
29 September 2020
22 -
23 June 2023
IRSN, Fontenay-aux-Roses, France
In the early decades of nuclear reactor development, many countries built and operated zero-power facilities in which many different critical arrangements of materials were studied. These flexible ex...
Published date:
6 June 2023
TCOFF-2 members discuss future activities.
Published date:
10 July 2023