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
International Conference on Nuclear Data for Science and Technology
Published date:
28 September 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
The expert group conducts joint and comparative studies to support the development, selection and characterisation of innovative structural materials that can be implemented in advanced nuclear fuel ...
Published date:
28 February 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...
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19 July 2022
Multi-physics Pellet Cladding Mechanical Interaction Validation (MPCMIV) Benchmark
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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 ...
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19 July 2022
TVA Watts Bar Unit 1 Multi-Physics Benchmark
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19 July 2022
The NEA Data Bank organised a PENELOPE training course at the University of Barcelona in Spain on 11-15 July 2022
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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...
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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 ...
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2 August 2022
NUPEC Boiling Water Reactor (BWR) Full-size Fine-mesh Bundle Test (BFBT) Benchmark
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2 August 2022
Forsmark 1 and 2 Boiling Water Reactor Stability Benchmark
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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 ...
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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.
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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...
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19 July 1995
The international benchmark concerned pebble bed modular reactor (PBMR) coupled neutronics/thermal-hydraulics transients based on the PBMR-400MW design.
