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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 1994
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1 January 1992
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1 January 1993
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1 January 1995
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1 January 1995
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1 January 1994
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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 1989
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1 January 2000
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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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20 June 2001
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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
Published date:
1 January 1999
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18 April 2006
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21 June 2007
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19 November 2004
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31 December 2004
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29 July 2005
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28 April 2005
Published date:
9 July 2004
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25 June 2004
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29 December 2006
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19 November 2004
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19 November 2004
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15 December 2004
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7 July 2005
Published date:
29 December 2006
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19 May 2006
Published date:
7 February 2006
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13 July 2009
Published date:
9 October 2009
Published date:
17 November 2009
Published date:
16 December 2009
Published date:
29 September 2011
Published date:
12 May 2010
Published date:
31 December 2013
Published date:
17 February 2015
Published date:
29 July 2015
Published date:
10 September 2015
Published date:
5 June 2007
NEA Framework for Irradiation Experiments (FIDES) flyer (October 2019)
Published date:
10 January 2020
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
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
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
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
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
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
Present Status of Minor Actinide Data
Published date:
1 January 1999
Nuclear Models to 200 MeV for High-Energy Data Evaluations
Published date:
1 January 1998
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
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
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
Published date:
23 February 2016
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
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
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
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
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
Published date:
30 October 2015
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
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
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
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
ICSBEP, SINBAD AND IRPhEP Technical Review Group meetings
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
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:
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
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1 January 1999
Published date:
1 January 1996
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1 January 1994
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1 January 1999
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1 January 1999
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1 January 1999
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1 January 1999
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1 January 1981
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1 January 1979
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1 January 1983
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1 January 1988
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1 January 1991
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1 January 1981
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1 January 1984
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1 January 1987
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1 January 1991
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1 January 2000
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14 February 2001
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25 October 2001
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4 February 2002
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30 August 2002
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9 May 2001
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11 January 2002
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22 May 2003
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11 August 2004
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20 October 2003
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19 July 2004
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26 October 2005
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20 July 2005
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27 October 2006
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18 December 2006
Published date:
26 June 2006
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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
Published date:
29 September 2020
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
The NEA nuclear science programme is developed and executed by the Nuclear Science Committee (NSC), comprising high-level scientific experts from all NEA member countries.
Published date:
6 December 2019
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
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
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
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
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 -
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
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/NSC/WPNCS/DOC(2011)5
Spent Nuclear Fuel Assay Data for Isotopic Validation - State-of-the-art Report
Published date:
6 June 2011
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
The NEA's nuclear data evaluation co-operation activities involve the following evaluation projects: ENDF (United States), JENDL (Japan), ROSFOND/BROND (Russia), JEFF (other Data Bank member countrie...
Published date:
9 March 2020
The task force developed best practice guidelines by performing a benchmark study on thermo-hydraulic modelling of heavy liquid metal coolant, e.g. lead and lead-bismuth eutectic (LBE) alloy.
Published date:
28 February 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
The expert group monitored the feedback from version 0 of the Lead-bismuth eutectic (LBE) handbook, collected, analysed and checked the consistency of expected new results from ongoing heavy liquid m...
Published date:
28 February 2020
NEA/NSC/DOC(2013)9
Workshop Proceedings, 10-12 December 2012
Published date:
25 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
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
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
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
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
