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:
22 September 2023
NEA/NSC/R(2023)8
The Task Force on Dose Rate Calculations for Irradiated Fuel Assembly was launched in 2015 to assess code predictions of dose rates from bare spent fuel assemblies and to benchmark multiple codes and...
Published date:
19 September 2023
NEA/NSC/R(2022)6
The goal of the Nuclear Energy Agency (NEA) Working Party on Nuclear Criticality Safety (WPNCS) Subgroup on Experimental Needs for Criticality Safety Purposes (SG-5) was to highlight the needs of int...
Published date:
15 September 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(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
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(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
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(2022)3/CORR
Please note that this report was initially published in November 2022 (NEA/NSC/R(2022)3) under erroneous benchmark number IIB; in this updated version (NEA/NSC/R(2022)3/CORR) this has been corrected ...
Published date:
30 November 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(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
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
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
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(2021)2
Proceedings of the Fourteenth Workshop, 30 October-2 November 2018, Gyeongju, Korea.
Published date:
16 December 2021
Published date:
8 December 2021
NEA/NSC/R(2020)7
In the past decade, a large amount of effort has been made towards the direct simulation of the boiling transition (BT) for boiling water reactor (BWR) fuel bundles. This international benchmark, bas...
Published date:
2 December 2021
NEA/NSC/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
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(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
Published date:
12 October 2020
Published date:
29 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/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
The NEA Annual Report 2019 provides an overview of the status of nuclear power in NEA member countries and illustrative descriptions of the Agency's activities and international joint projects. 2019 ...
Published date:
12 June 2020
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
NEA/NSC/DOC(2013)9
Workshop Proceedings, 10-12 December 2012
Published date:
25 February 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:
12 December 2018
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
The brochure provides background information about the NEA.
Published date:
10 September 2018
NEA/NSC/R(2018)1
LACANES – Phase II: Natural Convection
Published date:
4 April 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
Published date:
6 December 2017
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
Published date:
2 December 2016
Published date:
10 November 2016
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(2016)2
Numerical benchmark for the analysis of small-sample reactivity experiments
Published date:
9 June 2016
Published date:
23 February 2016
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
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)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
Published date:
10 September 2015
NEA/NSC/R(2015)5
State-of-the-Art Report on Multi-scale Modelling of Nuclear Fuels
Published date:
3 September 2015
Heavy liquid metals such as lead or lead-bismuth have been proposed and investigated as coolants for fast reactors since the 1950s. More recently, there has been renewed interest worldwide in the use...
Published date:
11 August 2015
Published date:
29 July 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)3
Twelfth Workshop Proceedings, Batavia, Illinois, United States, 28-30 April 2014
Published date:
2 June 2015
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/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
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
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
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
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
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
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
Published date:
16 May 2013
Published date:
31 December 2013
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
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
Published date:
29 September 2011
NEA/NSC/WPNCS/DOC(2011)5
Spent Nuclear Fuel Assay Data for Isotopic Validation - State-of-the-art Report
Published date:
6 June 2011
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
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
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
Hydrogen has the potential to play an important role as a sustainable and environmentally acceptable energy carrier in the 21st century. This report describes the scientific and technical challenges ...
Published date:
24 June 2010
Published date:
12 May 2010
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
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:
17 November 2009
Published date:
9 October 2009
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
NEA/NSC/DOC(2009)8
Saratoga Springs, New York, 6 May 2009 - Meeting summary
Published date:
11 May 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
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
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
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
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
Published date:
29 December 2006
Published date:
29 December 2006
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
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
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
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
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
Published date:
7 July 2006
Published date:
19 May 2006
Published date:
18 April 2006
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
Published date:
7 February 2006
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
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
Published date:
29 July 2005
Published date:
7 July 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:
7 July 2005
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
Published date:
28 April 2005
Published date:
15 December 2004
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
Published date:
9 July 2004
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
Published date:
25 June 2004
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
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
Published date:
31 December 2004
Published date:
8 August 2003
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
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
NEA/NSC/DOC(2003)1
21-22 January 2003, Barcelona, Spain
Published date:
1 May 2003
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(2002)15
6 October 2002, Seoul, Korea
Published date:
1 November 2002
Published date:
27 September 2002
NEA/NSC/DOC(2002)11
Rossendorf (Dresden), Germany, 28-30 May 2002
Published date:
29 July 2002
Published date:
21 February 2002
NEA/NSC/DOC(2002)2
Burn-up Calculations of BWR Fuel Assemblies for Storage and Transport
Published date:
16 January 2002
NEA/NSC/DOC(2001)20
Paul Scherrer Institute, Villigen, Switzerland, 15-16 October 2001
Published date:
1 October 2001
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
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
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
Published date:
22 December 2000
Published date:
10 December 2000
Published date:
8 December 2000
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(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
Published date:
1 January 2000
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
Published date:
1 January 1999
Published date:
1 January 1999
Present Status of Minor Actinide Data
Published date:
1 January 1999
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
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
NEA/NSC/DOC(1998)1
Results - Conceptual PWR Spent Fuel Transportation Cask, A. Nouri
Published date:
1 January 1998
Published date:
1 January 1998
Published date:
1 January 1998
Published date:
1 January 1998
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
NEA/NSC/DOC(1997)11
Hiroshi OKUNO, Yoshitaka NAITO and Yoshihira ANDO (JAERI)
Published date:
1 January 1997
Published date:
1 January 1997
Published date:
1 January 1997
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/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)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)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(1996)1
JAERI-Research 96-003, M. Takano, H. Okuno, (JAERI), publication date: February 1996
Published date:
1 January 1996
Published date:
1 January 1996
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
Published date:
1 January 1995
Published date:
1 January 1995
Published date:
1 January 1994
Published date:
1 January 1994
Published date:
1 January 1994
Published date:
1 January 1994
NEA/NSC/DOC(1993)22
JAERI-M-94-003 Makoto TAKANO (JAERI), January 1994
Published date:
1 January 1993
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
Published date:
1 January 1993
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
Published date:
1 January 1992
Published date:
1 January 1992
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/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
