The Working Party on Nuclear Criticality Safety (WPNCS) deals with technical and scientific issues relevant to criticality safety. Specific areas of interest include (but are not limited to) investig...
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17 May 2022
The Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC) studies advanced nuclear fuel cycles, including fuel cycle scenarios, innovative fuels and materials, separation chemistry, waste...
Published date:
24 February 2022
Under the guidance of the Working Party on Scientific Issues of Advanced Fuel Cycles (WPFC), the Expert Group on Fuel Recycling and Waste Technology (EGFRW) focuses on the separation processes releva...
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23 February 2022
Burn-up credit is a safety approach that accounts for the reduction in the reactivity of configurations with spent nuclear fuel due to the change in their composition after irradiation.
Published date:
21 January 2022
NEA/NSC/R(2021)2
Proceedings of the Fourteenth Workshop, 30 October-2 November 2018, Gyeongju, Korea.
Published date:
16 December 2021
NEA/NSC/R(2018)2
Published date:
8 December 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
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...
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18 November 2021
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15 October 2021
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15 October 2021
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15 October 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
NEA/NSC/R(2020)1
Since 2007, the NEA has organised a series of workshops on structural materials for innovative nuclear systems (SMINS). The fifth meeting, held from 8‑11 July 2019 in Kyoto, Japan, was hosted by Kyot...
Published date:
26 November 2020
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
NEA/NSC/R(2019)3
The Nuclear Energy Agency (NEA) Expert Group on Liquid Metal Technology (EGLM) conducted a survey to identify and establish common criteria and understanding on the complex issue of materials data se...
Published date:
20 October 2020
NEA/NSC/R(2019)5
Published date:
12 October 2020
NEA/NSC/R(2019)4
Published date:
12 October 2020
NEA Nuclear Science Committee (NSC) meeting, 23-25 September 2020.
Published date:
9 October 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:
1 October 2020
NEA/NSC/R(2019)2
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
New NEA reports on nuclear data evaluation
Published date:
5 August 2020
DATIF, the DATabase for IFpe, was first developed in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the NE...
Published date:
23 July 2020
Source Convergence in Criticality Safety Analyses - Phase II: Guidance for Analysts
Published date:
24 March 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
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
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
Thermal Scattering Law S(α,β): Measurement, Evaluation and Application
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13 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
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12 March 2020
Co-ordinated Evaluation of Plutonium-239 in the Resonance Region
Published date:
12 March 2020
WPEC Expert Group on the Recommended Definition of a General Nuclear Database Structure (EGGNDS) - Procedure for the Proposal and Approval of Changes to the GDNS Specifications, 25 June 2019
Published date:
11 March 2020
WPEC EGGNDS meeting, 25 June 2019 - agenda
Published date:
11 March 2020
Published date:
11 March 2020
Published date:
11 March 2020
Published date:
11 March 2020
Published date:
11 March 2020
Published date:
11 March 2020
Published date:
11 March 2020
WPEC EGGNDS meeting, 15 May 2017 - agenda
Published date:
11 March 2020
WPEC Subgroup 38 - Low-level data containers specifications for GNDS (DRAFT)
Published date:
11 March 2020
WPEC Subgroup 38 - Hierarchy specifications for GNDS (DRAFT)
Published date:
11 March 2020
Published date:
11 March 2020
WPEC Subgroup 38- Detailed requirements for a next generation nuclear data structure (GNDS), 5 July 2016, Brookhaven National Laboratory (BNL), US DOE, United States
Published date:
11 March 2020
- Annex 1. Mandate 2014-2016
- Annex 2. High priority request for the new measurements of the 237Np(n,f), by F Tovesson
- Annex 3.Specifications for the required changes of the new categories of request, ...
Published date:
11 March 2020
Published date:
11 March 2020
WPEC EGHPRL meeting, 18 May 2015 - summary record
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11 March 2020
Published date:
11 March 2020
Published date:
11 March 2020
Summary record of the HPRL meeting of 23 April 2007
Published date:
11 March 2020
Summary record of the HPRL meeting of 3 May 2006
Published date:
11 March 2020
Summary record of the HPRL meeting of 9-10 October 2003
Published date:
11 March 2020
WPEC EGHPRL meeting, 18 May 2015 - agenda
Published date:
11 March 2020
WPEC EGHPRL meeting, 9 May 2016 - agenda
Published date:
11 March 2020
WPEC EGHPRL meeting, 15 May 2017 - agenda
Published date:
11 March 2020
Published date:
11 March 2020
Published date:
11 March 2020
WPEC EGHPRL meeting, 25 June 2019 - agenda
Published date:
11 March 2020
WPEC EGHPRL meeting, 25 June 2019 - summary record
Published date:
11 March 2020
Published date:
11 March 2020
WPEC EGHPRL meeting, 16 May 2018 - agenda
Published date:
11 March 2020
2019 review of the HPRL system and IT infrastructure - NEA
Published date:
11 March 2020
WPEC EGHPRL meeting, 25 June 2019 - agenda
Published date:
11 March 2020
WPEC EGHPRL presentation - A. Koning et al., Coordination Action on Nuclear Data for Industrial Development in Europe (CANDIDE)
Published date:
11 March 2020
Published date:
10 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
Nuclear data thermal scattering
Published date:
9 March 2020
Nuclear data covariance and assimilation
Published date:
9 March 2020
Published date:
9 March 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
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:
9 March 2020
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:
9 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
WPNCS 2019 meetings - Subgroup 7 (SG-7) agenda
Published date:
6 March 2020
Ninth International Conference on Nuclear Criticality (ICNC2011) - Programme and call for papers
Published date:
6 March 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
Programme for the International Workshop on Nuclear Fuel Modelling to Support Safety and Performance Enhancement for Water-Cooled Reactors, 7-9 March 2017
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 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
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
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
Infographic for WPFC EGLM objectives
Published date:
4 March 2020
Third International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-3) – Programme
Published date:
3 March 2020
Fourth International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-4) – Programme
Published date:
3 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 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
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
Published date:
25 February 2020
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:
25 February 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
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
26 June 2019
NEA Headquarters, Boulogne-Billancourt, France
Published date:
12 March 2020
25 June 2019
NEA Headquarters, Boulogne-Billancourt, France
Published date:
11 March 2020
24 June 2019
NEA Headquarters, Boulogne-Billancourt, France
Published date:
12 March 2020
23 May 2019
ND2019, China National Convention Center, Beijing, China
Published date:
11 March 2020
22 May 2019
ND2019, China National Convention Center, Beijing, China
Published date:
12 March 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
NEA/NSC/R(2018)4
Published date:
12 December 2018
NEA/NSC/R(2018)3
To address the objective of the Expert Group on Innovative Structural Materials (EGISM) related to sharing available experimental installations, this report considers the existing facilities, also de...
Published date:
7 September 2018
16 May 2018
OECD Conference Centre, Paris, France
Published date:
11 March 2020
15 May 2018
OECD Conference Centre, Paris, France
Published date:
11 March 2020
14 May 2018
OECD Conference Centre, Paris, France
Published date:
12 March 2020
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
NEA/NSC/R(2017)4
Published date:
6 December 2017
NEA/NSC/R(2017)3
Published date:
25 July 2017
15 May 2017
OECD Conference Centre, Paris, France
Published date:
11 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
NEA/NSC/R(2017)2
Published date:
2 February 2017
NEA/NSC/R(2016)6
Published date:
2 December 2016
NEA/NSC/R(2016)5
Published date:
14 November 2016
NEA/NSC/R(2016)4
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
9 May 2016
OECD Conference Centre, Paris, France
Published date:
11 March 2020
NEA/NSC/R(2016)1
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)8
Published date:
30 October 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)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
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
18 May 2015
NEA Headquarters, Issy-les-Moulineaux, France
Published date:
11 March 2020
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/DOC(2015)7
Published date:
2 February 2015
NEA/NSC/WPFC/DOC(2015)9
Published date:
23 January 2015
NEA/NSC/DOC(2015)3
Published date:
21 January 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
NEA/NSC/DOC(2014)13
Published date:
24 July 2014
NEA/NSC/WPEC/DOC(2014)452
Published date:
23 May 2014
NEA/NSC/WPEC/DOC(2014)447
Published date:
31 March 2014
Meeting Nuclear Data Needs for Advanced Reactor Systems
Published date:
13 March 2014
NEA/NSC/WPEC/DOC(2014)446
Published date:
6 January 2014
Published date:
20 December 2013
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
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
NEA/NSC/WPEC/DOC(2013)445
Published date:
4 September 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
NEA/NSC/WPEC/DOC(2013)440
Published date:
29 May 2013
NEA/NSC/DOC(2013)7
Published date:
16 May 2013
NEA/NSC/DOC(2013)3
Published date:
23 January 2013
NEA/NSC/DOC(2013)1
The Expert Group on Reactor Physics and Advanced Nuclear Systems (EGRPANS) was created in 2011 to perform specific tasks associated with reactor physics aspects of present and future nuclear power sy...
Published date:
14 January 2013
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
NEA/NSC/WPEC/DOC(2012)438
Published date:
8 October 2012
NEA/NSC/WPFC/DOC(2012)15
Spent Nuclear Fuel Reprocessing Flowsheet
Published date:
12 June 2012
NEA/NSC/DOC(2012)12
Published date:
30 May 2012
Published date:
21 February 2012
NEA/NSC/WPFC/DOC(2012)2
Published date:
4 January 2012
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
NEA/NSC/WPEC/DOC(2011)433
Published date:
30 September 2011
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
NEA/NSC/WPEC/DOC(2011)432
Published date:
15 September 2011
NEA/NSC/DOC(2011)5
Published date:
16 June 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
NEA/NSC/DOC(2011)4
Published date:
6 May 2011
NEA/NSC/WPEC/DOC(2011)430
Published date:
1 April 2011
NEA/NSC/WPEC/DOC(2010)429
Published date:
21 December 2010
NEA/NSC/WPEC/DOC(2010)427
Published date:
17 December 2010
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
NEA/NSC/DOC(2010)7
Published date:
18 March 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
NEA/NSC/DOC(2010)6
Published date:
3 March 2010
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
NEA/EANDC(1960)5/U
Published date:
24 August 2009
NEA/NEANDC(1979)125/U
Published date:
19 August 2009
NEA/NEANDC(1980)128/U
Published date:
18 August 2009
NEA/NEANDC(1981)148/U
Published date:
16 July 2009
NEA/NSC/WPEC/DOC(2009)415
Published date:
29 June 2009
NEA/NSC/DOC(2009)13
Published date:
16 June 2009
NEA/NSC/DOC(2009)11
Published date:
19 May 2009
NEA/NSC/DOC(2009)7
Published date:
11 May 2009
NEA/NSC/DOC(2009)6
Published date:
18 March 2009
NEA/NSC/DOC(2009)2
Published date:
6 March 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
Published date:
9 September 2008
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
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
NEA/NSC/WPEC/DOC(2006)378
Published date:
8 July 2008
NEA/NSC/DOC(2008)8
Published date:
11 June 2008
NEA/NSC/DOC(2008)7
Published date:
27 May 2008
NEA/NSC/DOC(2008)6
Published date:
11 April 2008
NEA/NSC/DOC(2008)5
Garching, Germany, 31 March -1 April 2008
Published date:
9 April 2008
NEA/NSC/DOC(2008)4
Published date:
4 February 2008
NEA/NSC/DOC(2008)3
Published date:
22 January 2008
NEA/NSC/DOC(2007)25
Published date:
19 December 2007
NEA/NSC/DOC(2007)23
Published date:
4 December 2007
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
NEA/NSC/DOC(2007)17
Published date:
25 September 2007
NEA/NSC/DOC(2007)16
Paris, France, 8-9 May 2007
Published date:
19 September 2007
NEA/NSC/DOC(2007)15
Published date:
17 September 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
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
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)11
Published date:
30 May 2007
NEA/NSC/DOC(2007)9
Published date:
18 May 2007
NEA/NSC/DOC(2007)8
Monterey, California, USA, 17 April 2007
Published date:
15 May 2007
NEA/NSC/DOC(2007)6
Published date:
26 March 2007
NEA/NSC/DOC(2007)5
Published date:
24 March 2007
NEA/NSC/DOC(2007)4
Published date:
21 March 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
NEA/NSC/DOC(2006)31
Published date:
19 January 2007
Published date:
20 December 2006
NEA/NSC/DOC(2006)30
Published date:
13 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
NEA/NSC/DOC(2006)26
Published date:
8 November 2006
NEA/NSC/DOC(2006)24
Published date:
11 October 2006
NEA/NSC/DOC(2006)21
Published date:
21 September 2006
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
NEA/NSC/DOC(2006)17
Published date:
16 June 2006
NEA/NSC/DOC(2006)14
Pisa, Italy, 26-27 April 2006
Published date:
8 May 2006
NEA/NSC/DOC(2006)13
Published date:
5 May 2006
NEA/NSC/DOC(2006)9
Published date:
13 February 2006
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
NEA/NSC/DOC(2005)31
Published date:
9 December 2005
NEA/NSC/DOC(2005)27
Published date:
7 December 2005
NEA/NSC/DOC(2005)25
Published date:
21 November 2005
NEA/NSC/DOC(2005)23
Published date:
14 November 2005
NEA/NSC/DOC(2006)2
Published date:
11 November 2005
NEA/NSC/DOC(2005)19
27-29 June 2005, University Park, PA, USA
Published date:
10 October 2005
NEA/NSC/DOC(2005)18
Published date:
7 October 2005
NEA/NSC/DOC(2005)17
Published date:
5 September 2005
NEA/NSC/DOC(2005)15
Published date:
25 August 2005
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
NEA/NSC/DOC(2005)6
Published date:
10 May 2005
NEA/NSC/WPEC/DOC(2005)367
Published date:
10 April 2005
NEA/NSC/DOC(2005)2
Published date:
28 February 2005
NEA/NSC/DOC(2004)15
4 October 2004, Nara, Japan
Published date:
4 November 2004
NEA/NSC/DOC(2004)14
Published date:
20 October 2004
NEA/NSC/WPEC/DOC(2004)298
Published date:
1 June 2004
NEA/NSC/DOC(2004)7
Published date:
17 March 2004
NEA/NSC/DOC(2004)4
Published date:
2 February 2004
NEA/SEN/NSC/WPPR(2004)1
Published date:
13 January 2004
NEA/NSC/WPEC/DOC(2003)295
Published date:
10 December 2003
NEA/NSC/WPEC/DOC(2003)294
Published date:
12 November 2003
NEA/NSC/WPEC/DOC(2003)293
Published date:
16 October 2003
NEA/NSC/DOC(2003)18
Published date:
21 July 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/WPEC/DOC(2003)292
Published date:
27 June 2003
NEA/NSC/WPEC/DOC(2003)271
Published date:
26 June 2003
NEA/NSC/DOC(2003)17
Published date:
3 June 2003
NEA/NSC/DOC(2003)13
Published date:
19 May 2003
Published date:
16 May 2003
NEA/NSC/DOC(2003)1
21-22 January 2003, Barcelona, Spain
Published date:
1 May 2003
NEA/NSC/DOC(2003)7
Published date:
30 April 2003
NEA/NSC/DOC(2003)3
Reactivity Prediction Calculations for Infinite Arrays of PWR Mox Fuel Pincells
Published date:
17 April 2003
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
NEA/NSC/DOC(2002)15
6 October 2002, Seoul, Korea
Published date:
1 November 2002
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
Delayed Neutron Data for the Major Actinides
Published date:
11 October 2002
NEA/NSC/WPEC/DOC(2002)257
Published date:
1 October 2002
NEA/NSC/DOC(2002)11
Rossendorf (Dresden), Germany, 28-30 May 2002
Published date:
29 July 2002
NEA/NSC/DOC(2002)10
Published date:
18 July 2002
NEA/NSC/DOC(2002)8
Published date:
2 July 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)19
Published date:
6 November 2001
NEA/NSC/DOC(2001)20
Paul Scherrer Institute, Villigen, Switzerland, 15-16 October 2001
Published date:
1 October 2001
Evaluation Method of Inelastic Scattering Cross-sections for Weakly Absorbing Fission-product Nuclides
Published date:
21 September 2001
NEA/NSC/DOC(2001)15
Published date:
27 July 2001
NEA/NSC/DOC(2001)13
Published date:
18 June 2001
NEA/NSC/WPEC/DOC(1997)156
Published date:
25 May 2001
NEA/NSC/WPEC/DOC(1999)201
Published date:
23 May 2001
NEA/NSC/DOC(2001)10
Published date:
10 May 2001
NEA/NSC/DOC(2001)8
Published date:
10 April 2001
NEA/NSC/DOC(2001)2
Published date:
28 February 2001
Processing and Validation of Intermediate Energy Evaluated Data Files
Published date:
28 December 2000
NEA/NSC/DOC(2000)22
Published date:
10 December 2000
NEA/NSC/DOC(2000)15
Published date:
4 August 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)7
Published date:
30 March 2000
NEA/NSC/DOC(2000)6
Published date:
17 March 2000
NEA/NSC/DOC(2000)3
Published date:
24 February 2000
NEA/NEACRP/A(1973)215
Published date:
13 January 2000
NEA/NEACRP/A(1971)177
Published date:
12 January 2000
NEA/NEANDC(1989)253/U
Published date:
7 January 2000
NEA/NEACRP/A(1970)133
Published date:
5 January 2000
NEA/SEN/NSC/WPPR(1999)4
Published date:
13 December 1999
NEA/NSC/DOC(1999)15
Published date:
6 December 1999
NEA/NEANDC(1984)53/L
Published date:
22 October 1999
NEA/NSC/DOC(1992)14
Published date:
15 October 1999
NEA/SEN/NSC/WPPR(1996)5
Published date:
7 October 1999
NEA/SEN/NSC/WPPR(1998)1
Published date:
20 September 1999
NEA/NSC/WPEC/DOC(1998)189/bis
Published date:
12 August 1999
NEA/NSC/DOC(1993)25
Published date:
6 August 1999
NEA/NSC/DOC(1995)15/CORR
Published date:
22 July 1999
NEA/NEACRP/L(1983)265
Published date:
5 July 1999
NEA/NEACRP/L(1974)111
Published date:
29 June 1999
NEA/NSC/WPEC/DOC(1998)183
Published date:
14 June 1999
NEA/NSC/WPEC/DOC(1998)174
Published date:
11 June 1999
NEA/NSC/WPEC/DOC(1997)166
Published date:
10 June 1999
NEA/NSC/WPEC/DOC(1997)152
Published date:
9 June 1999
NEA/NSC/DOC(1999)10
Published date:
20 May 1999
NEA/NSC/DOC(1999)9
Published date:
17 May 1999
NEA/SEN/NSC/WPPR(1999)1
Published date:
3 May 1999
NEA/NSC/DOC(1999)5
Published date:
27 April 1999
NEA/NSC/DOC(1999)2
Published date:
22 January 1999
Epithermal Capture Cross-Section of U-235
Published date:
1 January 1999
Status of Pseudo-Fission-Product Cross-Sections for Fast Reactors
Published date:
1 January 1998
NEA/NSC/DOC(1997)2
Published date:
1 January 1997
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
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
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
NEA/NSC/WPEC/DOC(1995)121
Published date:
1 January 1995
NEA/NSC/WPEC/DOC(1994)89
Published date:
1 January 1994
NEA/NSC/WPEC/DOC(1993)77
Published date:
1 January 1993
NEA/NEACRP/L(1992)339
Published date:
1 January 1992
NEA/NEANDC(1991)305/U
Published date:
1 January 1991
NEA/NEANDC(1990)292/U
Published date:
1 January 1990
NEA/NEANDC(1989)272/U
Published date:
1 January 1989
NEA/NEACRP/L(1988)307
Published date:
1 January 1988
NEA/NEACRP/L(1987)301
Published date:
1 January 1987
NEA/NEACRP/L(1986)295
Published date:
1 January 1986
NEA/NEACRP/L(1985)286
Published date:
1 January 1985
