Publications and reports available on the NEA website


General information Year
7404 NEA 2017 Annual Report 2018
7349 NEA Annual Report 2016 2017
7347 NEA News Vol. 35.1 2017
7350 Rapport annuel 2016 de l'AEN 2017
7293 Annual Report 2015 2016
7243 NEA News Vol. 33 No. 2 2016
7292 NEA News Vol. 34.2 2016
7291 NEA News, No. 34.1 2016
7295 NEA Strategic Plan 2017-2022 2016
7296 Plan stratégique de l'AEN 2017-2022 2016
7294 Rapport Annuel 2015 2016
7240 AEN Infos, Vol 32.1-32.2 2015
7238 Annual Report 2014 2015
7241 NEA News Vol. 33 No. 1 2015
7239 Rapport Annuel 2014 2015
7177 AEN Infos, n° 32-1/32-2 2014
7174 Annual Report 2013 2014
7176 NEA News, No. 32-1/32-2 2014
7175 Rapport annuel 2013 2014
7165 AEN Infos vol. 30.2-31.1 2013
7144 Annual Report 2012 2013
7142 L'Agence de l'OCDE pour l'énergie nucléaire 2013
7164 NEA News No. 30.2-31.1 2013
7169 NEA News, No. 31-2 2013
7145 Rapport annuel 2012 2013
7139 The OECD Nuclear Energy Agency 2013
7158 Агентство по ядерной энергии ОЭСР Russian version of "The OECD Nuclear Energy Agency" 2013
7149 经济合作与发展组织核能署 Chinese translation of The OECD Nuclear Energy Agency 2013
7097 AEN Infos, vol. 30 n° 1 2012
7094 Annual Report 2011 2012
7109 L'Agence de l'OCDE pour l'énergie nucléaire 2012
7096 NEA News, Vol. 30 No. 1 2012
6888 OECD Nuclear Energy Agency (NEA) follow-up to the TEPCO Fukushima Daiichi nuclear accident Extracts from NEA News 2012
7095 Rapport annuel 2011 2012
7108 The OECD Nuclear Energy Agency 2012
7008 AEN Infos, vol. 29 n° 1 2011
7010 AEN Infos, vol. 29 n° 2 2011
7005 Annual Report 2010 2011
7019 Executive Summary of the Security of Energy Supply and the Contribution of Nuclear Energy 2011
7012 L'Agence pour l'énergie nucléaire (AEN) en bref 2011
7026 La sécurité d'approvisionnement énergétique et le rôle du nucléaire (Résumé) 2011
7007 NEA News, Vol. 29 No. 1 2011
7009 NEA News, Vol. 29 No. 2 2011
7006 Rapport annuel 2010 2011
7011 The Nuclear Energy Agency (NEA) in Brief 2011
6928 AEN Infos 28.1 (Juin 2010) 2010
6930 AEN Infos 28.2 (Décembre 2010) 2010
6931 Annual Report 2009 2010
6957 Coûts prévisionnels de production de l'électricité - Edition 2010 - Synthèse 2010
6963 L'énergie nucléaire et le changement climatique (brochure) 2010
6960 Le plan stratégique de l'Agence pour l'énergie nucléaire - 2011-2016 2010
6927 NEA News 28.1 (June 2010) 2010
6929 NEA News 28.2 (December 2010) 2010
6956 Projected Costs of Generating Electricity - 2010 Edition - Executive Summary 2010
6932 Rapport annuel 2009 2010
6959 The Strategic Plan of the Nuclear Energy Agency - 2011-2016 2010
6841 AEN Infos 27.2 (Décembre 2009) 2009
6839 AEN infos 27.1 (Juin 2009) 2009
6842 Annual Report 2008 2009
6838 NEA News 27.1 (June 2009) 2009
6840 NEA News 27.2 (December 2009) 2009
6883 Nuclear Energy and Addressing Climate Change (brochure) 2009
6843 Rapport annuel 2008 2009
6371 Annual Report 2007 2008
6366 Brochure 50e anniversaire de l'Agence 2008
6365 NEA 50th Anniversary Historical Review 2008
6367 NEA News 26 2008
6372 Rapport annuel 2007 2008
6269 AEN Infos 25.1 2007
6271 AEN Infos 25.2 2007
6266 Annual Report 2006 2007
6268 NEA News 25.1 2007
6270 NEA News 25.2 2007
6140 AEN Infos - 2006 - no 24.1 2006
6142 AEN Infos - 2006 - n° 24.2 2006
6143 Annual Report 2005 2006
6139 NEA News - 2006 - No. 24.1 2006
6141 NEA News - 2006 - No. 24.2 2006
6144 Rapport annuel 2005 2006
6008 AEN Infos - 2005 - n° 23.1 2005
6010 AEN Infos - 2005 - n° 23.2 2005
6019 Annual Report 2004 2005
6007 NEA News - 2005 - No. 23.1 2005
6009 NEA News - 2005 - No. 23.2 2005
6020 Rapport annuel 2004 2005
5228 AEN Infos - 2004 - no. 22.1 2004
5311 AEN Infos - 2004 - no. 22.2 2004
5329 Annual Report 2003 2004
5748 Le plan stratégique de l'Agence pour l'énergie nucléaire - 2005-2009 2004
5208 NEA News - 2004 - No. 22.1 2004
5310 NEA News - 2004 - No. 22.2 2004
5330 Rapport annuel 2003 2004
5729 The Strategic Plan of the Nuclear Energy Agency - 2005-2009 2004
4313 AEN Infos - 2003 - no. 21.1 2003
4315 AEN Infos - 2003 - no. 21.2 2003
4368 Annual Report 2002 2003
4312 NEA News - 2003 - No. 21.1 2003
4314 NEA News - 2003 - No. 21.2 2003
4369 Rapport annuel 2002 2003
3649 AEN Infos - 2002 - no. 20.1 2002
3651 AEN Infos - 2002 - no. 20.2 2002
3666 Annual Report 2001 2002
3648 NEA News - 2002 - No. 20.1 2002
3650 NEA News - 2002 - No. 20.2 2002
3069 AEN Infos - 2001 - no. 19.1 2001
3089 AEN Infos - 2001 - no. 19.2 2001
3110 Annual Report 2000 2001
3113 Brochure AEN 2001
3088 NEA News - 2001 - No. 19.2 2001
3068 NEA News - 2001 - No.19.1 2001
3112 NEA brochure 2001
3111 Rapport annuel 2000 2001
2451 AEN Infos 2000 - no. 18.1 2000
2808 AEN Infos 2000 - no. 18.2 2000
2508 Annual Report 1999 2000
2548 Geologic Disposal of Radioactive Waste in Perspective 2000
2531 Le point sur l'évacuation des déchets radioactifs en formations géologiques 2000
2450 NEA News 2000 - No. 18.1 2000
2788 NEA News 2000 - No. 18.2 2000
1607 Annual Report 1998 1999
2069 Bulletin AEN Volume 17, no.2 - 1999 1999
1688 Bulletin AEN Volume 17, no1 - 1999 1999
1687 NEA Newsletter Volume 17, no.1 - 1999 1999
2068 NEA Newsletter Volume 17, no. 2 - 1999 1999
1608 Rapport Annuel 1998 Vingt-septième rapport annuel de l'Agence de l'OCDE pour l'énergie nucléaire 1999
1387 Bulletin de l'AEN Volume 16 no.2 - 1998 1998
1568 Le plan stratégique de l'Agence pour l'énergie nucléaire - 1999 1998
1367 NEA Newsletter Volume 16 no.2 - 1998 1998
1006 NEA Newsletter Volume 16 No.1 -1998 1998
587 Nuclear Energy in the OECD Towards an Integrated Approach 1998
1567 The Strategic Plan of the Nuclear Energy Agency - 1999 1998
828 Bulletin AEN Volume 15 no2 - 1997 1997
277 Bulletin de l'AEN (printemps 1997) 1997
827 NEA Newsletter Volume 15 no.2 - 1997 1997
276 NEA Newsletter (Spring 1997) 1997
69 EUROCHEMIC 1956-1990 : 35 Ans de coopération internationale dans le domaine des techniques nucléaires 1996
68 EUROCHEMIC 1956-90: 35 Years of International Experience in the Field of Nuclear Techniques 1996
33 NEA Statute 1995
42 NEA Issue Briefs Radiation Protection Overview: International Aspects and Perspective 1994
44 NEA Issue Briefs International Nuclear Third Party Liability [Rev. 1] 1993
49 NEA Issue Briefs Broad Impact of Nuclear Power 1993
48 NEA Issue Briefs Probabilistic Safety Assessment: An Analytical Tool for Assessing Nuclear Safety 1992
47 NEA Issue Briefs Small and Medium Reactors 1990
43 NEA Issue Briefs Disposal of High-Level Radioactive Waste (The) 1989
46 NEA Issue Briefs Management of Low and Intermediate-level Radioactive Waste (The) 1989
45 NEA Issue Briefs Advanced Water Reactor Technology 1989
41 NEA Issue Briefs Human Factor in Nuclear Power Plant Operations (The) 1988
Nuclear science Year
7267 State-of-the-art Report on the Progress on Nuclear Fuel Cycle Chemistry 2018
7329 International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhe Project) 2017
7391 SFCOMPO-2.0: International Database of Spent Nuclear Fuel Isotopic Assays 2017
7328 International Handbook of Evaluated Criticality Safety Benchmark Experiments 2016
7268 Handbook on Lead-bismuth Eutectic Alloy and Lead Properties, Materials Compatibility, Thermal-hydraulics and Technologies 2015
7281 International Handbook of Evaluated Criticality Safety Benchmark Experiments 2015
7258 International Handbook of Evaluated Reactor Physics Benchmark Experiments 2015
7224 Introduction of Thorium in the Nuclear Fuel Cycle Short- to long-term considerations 2015
7228 Perspectives on the Use of Thorium in the Nuclear Fuel Cycle – Extended Summary 2015
7222 Review of Integral Experiments for Minor Actinide Management 2015
7231 International Handbook of Evaluated Criticality Safety Benchmark Experiments 2014
7173 International Handbook of Evaluated Reactor Physics Benchmark Experiments 2014 Edition 2014
6895 State-of-the-art Report on Innovative Fuels for Advanced Nuclear Systems 2014
6355 Chemical Thermodynamics of Iron, Part I, Volume 13a 2013
7171 International Evaluation Co-operation (Vol. 33) Methods and Issues for the Combined Use of Integral Experiments and Covariance Data (Volume 33) 2013
7140 International Handbook of Evaluated Reactor Physics Benchmark Experiments (DVD) March 2013 2013
6997 Minor Actinide Burning in Thermal Reactors A Report by the Working Party on Scientific Issues of Reactor Systems 2013
7157 Shielding Aspects of Accelerators, Targets and Irradiation Facilities -- SATIF-11 Workshop Proceedings, Tsukuba, Japan, 11-13 September 2012 2013
6409 Status Report on Structural Materials for Advanced Nuclear Systems 2013
7079 Validation of the JEFF-3.1 Nuclear Data Library JEFF Report 23 2013
6996 Actinide and Fission Product Partitioning and Transmutation Eleventh Information Exchange Meeting, San Francisco, California, USA, 1-4 November 2010 2012
6998 Burn-up Credit Criticality Safety Benchmark – Phase VII UO2 Fuel: Study of Spent Fuel Compositions for Long-term Disposal 2012
6354 Chemical Thermodynamics of Tin Chemical Thermodynamics Volume 12 2012
7077 Homogeneous versus Heterogeneous Recycling of Transuranics in Fast Nuclear Reactors 2012
7038 International Handbook of Evaluated Criticality Safety Benchmark Experiments September 2011 2012
7080 International Handbook of Evaluated Criticality Safety Benchmark Experiments (DVD) 2012
7081 International Handbook of Evaluated Reactor Physics Benchmark Experiments (DVD) 2012
7111 JEFF 3.1.2 Joint Evaluated Nuclear Data Library for Fission and Fusion Applications February 2012 2012
7116 Janis 3.4 A Java-based Nuclear Data Display Program 2012
6896 Structural Materials for Innovative Nuclear Systems (SMINS-2) Workshop Proceedings, Daejon, Republic of Korea, 31 August-3 September 2010 2012
6894 Potential Benefits and Impacts of Advanced Nuclear Fuel Cycles with Actinide Partitioning and Transmutation 2011
6897 Technology and Components of Accelerator-driven Systems Workshop Proceedings, Karlsruhe, Germany, 15-17 March 2010 2011
6420 Actinide and Fission Product Partitioning and Transmutation + CD-ROM Tenth Information Exchange Meeting, Mito, Japan, 6-10 October 2008 2010
6050 Boiling Water Reactor Turbine Trip (TT) Benchmark - Vol. IV Volume IV: Summary Results of Exercise 3 2010
6942 International Nuclear Data Evaluation Co-operation - CD-ROM Complete Collection of Published Reports as of January 2010 2010
6343 NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) Benchmark (Vol. II) Volume II: Uncertainty and Sensitivity Analyses of Void Distribution and Critical Power - Specification 2010
5425 National Programmes in Chemical Partitioning A Status Report 2010
6805 Nuclear Production of Hydrogen Fourth Information Exchange Meeting, Oakbrook, Illinois, United States, 13-16 April 2009 2010
6947 Research and Test Facilities Required in Nuclear Science and Technology (Japanese version) 原子力の科学技術で必要とされる試験研究施設 2010
6898 Shielding Aspects of Accelerators,Targets and Irradiation Facilities - SATIF-10 Workshop Proceedings, Geneva, Switzerland, 2-4 June 2010 2010
6964 VVER-1000 Coolant Transient Benchmark Phase 2 (V1000CT-2) Summary Results of Exercise 1 on Vessel Mixing Simulation 2010
6849 Besoins d'installations de recherche et d'expérimentation en sciences et technologies nucléaires 2009
6254 Chemical Thermodynamics of Thorium - Volume 11 2009
6283 Evaluated Data Library for the Bulk of Fission Products (Volume 23) International Evaluation Co-operation, Volume 23 2009
6881 Independent Evaluation of the MYRRHA Project Report by an International Team of Experts 2009
6285 Inter-code Comparison Exercise for Criticality Excursion Analysis Benchmarks Phase I: Pulse Mode Experiments with Uranyl Nitrate Solution Using the TRACY and SILENE Experimental Facilities 2009
6291 Mixed-oxide (MOX) Fuel Performance Benchmark (PRIMO) Summary of the Results for the PRIMO BD8 MOX Rod 2009
6310 Mobile Fission and Activation Products in Nuclear Waste Disposal Workshop Proceedings, La Baule, France, 16-19 January 2007 2009
6857 Nuclear Fuel Cycle Synergies and Regional Scenarios for Europe 2009
6194 Nuclear Fuel Cycle Transition Scenario Studies Status Report 2009
6416 PENELOPE-2008: A Code System for Monte Carlo Simulation of Electron and Photon Transport Workshop Proceedings, Barcelona, Spain, 30 June-3 July 2008 2009
6293 Research and Test Facilities Required in Nuclear Science and Technology 2009
6807 The JEFF-3.1.1 Nuclear Data Library JEFF Report 22 - Validation Results from JEF-2.2 to JEFF-3.1.1 2009
6287 The JEFF-3.1/-3.1.1 Radioactive Decay Data and Fission Yields Sub-libraries JEFF Report 20 2009
6292 Analytical Benchmarks for Nuclear Engineering Applications Case Studies in Neutron Transport Theory 2008
6410 International Evaluation Co-operation (Vol. 26) + CD-ROM Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations (Volume 26) 2008
6260 Structural Materials for Innovative Nuclear Systems (SMINS) Workshop Proceedings, Karlsruhe, Germany, 4-6 June 2007 2008
6259 Utilisation and Reliability of High Power Proton Accelerators (HPPA5) Workshop Proceedings, Mol, Belgium, 6-9 May 2007 2008
6282 Actinide and Fission Product Partitioning and Transmutation Ninth Information Exchange Meeting, Nîmes, France, 25-29 September 2006 2007
6284 Assessment of Fission Product Decay Data for Decay Heat Calculations International Evaluation Co-operation, Volume 25 2007
5435 Burn-up Credit Criticality Benchmark - Phase II-C Phase II-C: Impact of the Asymmetry of PWR Axial Burn-up Profiles on the End Effect 2007
6255 Chemical Thermodynamics of Solid Solutions of Interest in Nuclear Waste Management - Volume 10 A State-of-the-art Report 2007
6195 Handbook on Lead-bismuth Eutectic Alloy and Lead Properties, Materials Compatibility, Thermal-hydraulics and Technologies + CD-ROM 2007
4450 Mixed-oxide (MOX) Fuel Performance Benchmark Summary of the Results for the Halden Reactor Project MOX Rods 2007
4440 Physics of Plutonium Recycling - Volume IX Volume IX: Benchmark on Kinetic Parameters in the CROCUS Reactor 2007
6200 Physics of Plutonium Recycling - Volume VIII Volume VIII: Results of a Benchmark Considering a High-temperature Reactor (HTR) Fuelled with Reactor-grade Plutonium 2007
6288 Speciation Techniques and Facilities for Radioactive Materials at Synchrotron Light Sources Workshop Proceedings, Karlsruhe, Germany, 18-20 September 2006 2007
6201 VVER-1000 Coolant Transient Benchmark - Phase 1 (Vol. 3) Phase I (V1000CT-1), Vol. 3: Summary Results of Exercise 2 on Coupled 3-D Kinetics/Core Thermal-hydraulics 2007
3130 Benchmark on the KRITZ-2 LEU and MOX Critical Experiments Final Report 2006
6051 Besoins de R-D pour les systèmes nucléaires actuels et futurs 2006
5437 Boiling Water Reactor Turbine Trip (TT) Benchmark - Volume III Volume III: Summary Results of Exercise 2 2006
6227 Burn-up Credit Criticality Benchmark - Phase II-D PWR-UO2 Assembly - Study of Control Rod Effects on Spent Fuel Composition 2006
4439 Computer Simulation of MASURCA Critical and Subcritical Experiments MUSE-4 Benchmark - Final Report 2006
6198 International Evaluation Co-operation (Vol. 20) Covariance Matrix Evaluation and Processing in the Resolved/Unresolved Resonance Regions (Volume 20) 2006
6199 International Evaluation Co-operation (Vol. 22) Nuclear Data for Improved LEU-LWR Reactivity Predictions (Volume 22) 2006
6197 International Evaluation Co-operation (Vol. 7) Nuclear Data Standards (Volume 7) 2006
6212 NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) Benchmark Volume I: Specifications 2006
6122 Nuclear Production of Hydrogen Third Information Exchange Meeting, Oarai, Japan, 5-7 October 2005 2006
6222 PENELOPE-2006: A Code System for Monte Carlo Simulation of Electron and Photon Transport Workshop Proceedings, Barcelona, Spain, 4-7 July 2006 2006
6121 Perspectives on Nuclear Data for the Next Decade Workshop Proceedings, Bruyères-le-Châtel, France, 26-28 September 2005 2006
6090 Physics and Safety of Transmutation Systems A Status Report 2006
6048 Pressurised Water Reactor MOX/UO2 Core Transient Benchmark Final Report 2006
5433 Reference Values for Nuclear Criticality Safety + CD-ROM 2006
5431 Source Convergence in Criticality Safety Analyses Phase I: Results for Four Test Problems 2006
6046 Speciation Techniques and Facilities for Radioactive Materials at Synchrotron Light Sources Workshop Proceedings, Berkeley, California, USA, 14-16 September 2004 2006
6190 The JEFF-3.1 Nuclear Data Library JEFF Report 21 2006
6192 VENUS-2 MOX-fuelled Reactor Dosimetry Calculations Final Report 2006
6219 VVER-1000 Coolant Transient Benchmark (Vol. II) Phase 1 (V1000CT-1), Vol. 2: Summary Results of Exercise 1 on Point Kinetics Plant Simulation 2006
6088 VVER-1000 MOX Core Computational Benchmark Specification and Results 2006
6224 Very High Burn-ups in Light Water Reactors 2006
5421 Accelerator and Spallation Target Technologies for ADS Applications A Status Report 2005
5420 Benchmark on Deterministic Transport Calculations Without Spatial Homogenisation MOX Fuel Assembly 3-D Extension Case 2005
4448 Boiling Water Reactor Turbine Trip (TT) Benchmark - Volume II Volume II: Summary Results of Exercise 1 2005
6047 Evaluation of Proposed Integral Critical Experiments with Low-moderated MOX Fuel 2005
5419 Fuels and Materials for Transmutation A Status Report 2005
5426 International Evaluation Co-operation (Vol. 19) Neutron Activation Cross-section Measurements from Threshold to 20 MeV for the Validation of Nuclear Models and Their Parameters (Volume 19) 2005
5428 International Evaluation Co-operation (Vol. 21) Assessment of Neutron Cross-section Evaluations for the Bulk of Fission Products (Volume 21) 2005
6071 JEFF 3.1 (CD-ROM) 2005
6004 Pellet-clad Interaction in Water Reactor Fuels Seminar Proceedings, Aix-en-Provence, France, 9-11 March 2004 2005
6005 Shielding Aspects of Accelerators, Targets and Irradiation Facilities - SATIF 7 Workshop Proceedings, Lisbon, Portugal, 17-18 May 2004 2005
6068 The JEFF-3.0 Nuclear Data Library (Reprint) JEFF Report 19 - Synopsis of the General Purpose File 2005
6003 Utilisation and Reliability of High Power Proton Accelerators Workshop Proceedings, Daejeon, Republic of Korea, 16-19 May 2004 2005
5309 Basic Studies in the Field of High-temperature Engineering Third Information Exchange Meeting, Ibaraki-ken, Japan, 11-12 September 2003 2004
5422 Benchmark on Beam Interruptions in an Accelerator-driven System Final Report on Phase II Calculations 2004
4438 Benchmark on the Three-dimensional VENUS-2 MOX Core Measurements Final Report 2004
3713 Chemical Thermodynamics of Americium (reprint) (Volume 2) Reprint of the 1995 Review 2004
3712 Chemical Thermodynamics of Uranium (reprint) (Volume 1) Reprint of the 1992 Review 2004
4311 Computing Radiation Dosimetry - CRD 2002 Workshop Proceedings, Sacavém, Portugal, 22-23 June 2002 2004
3728 JANIS - Version 2.0 (A Java-based Nuclear Data Display Program) 2004
5688 JANIS 2.1 (DVD) 2004
4452 Neutronics/Thermal-hydraulics Coupling in LWR Technology, Vol. 1 CRISSUE-S - WP1: Data Requirements and Databases Needed for Transient Simulations and Qualification - 5th EURATOM Framework Programme (1998-2002) 2004
5436 Neutronics/Thermal-hydraulics Coupling in LWR Technology, Vol. 2 CRISSUE-S - WP2: State-of-the-art Report - 5th EURATOM Framework Programme (1998-2002) 2004
5434 Neutronics/Thermal-hydraulics Coupling in LWR Technology, Vol. 3 CRISSUE-S - WP3: Achievements and Recommendations Report - 5th EURATOM Framework Programme (1998-2002) 2004
5308 Nuclear Production of Hydrogen Second Information Exchange Meeting, Argonne, Illinois, USA, 2-3 October 2003 2004
5427 Pyrochemical Separations in Nuclear Applications A Status Report 2004
5808 Research and Development Needs for Current and Future Nuclear Energy Systems (Japanese translation) 2004
3828 Shielding Aspects of Accelerators, Targets and Irradiation Facilities - SATIF 6 Workshop Proceedings, Stanford, California, USA, 10-12 April 2002 2004
3711 The JEFF-3.0 Nuclear Data Library JEFF Report 19 2004
5668 The Need for Integral Critical Experiments with Low-moderated MOX Fuels Workshop Proceedings, Paris, France, 14-15 April 2004 2004
4454 Actinide and Fission Product Partitioning and Transmutation Seventh Information Exchange Meeting, Jeju, Republic of Korea, 14-16 October 2002 2003
3136 Benchmark on Beam Interruptions in an Accelerator-driven system Final Report on Phase I Calculations 2003
3135 Benchmark on Deterministic Transport Calculations Without Spatial Homogenisation A 2-D/3-D MOX Fuel Assembly Benchmark 2003
3694 Burn-up Credit Criticality Benchmark - Phase IV-A Phase IV-A: Reactivity Prediction Calculations for Infinite Arrays of PWR MOX Fuel Pin Cells 2003
3709 Burn-up Credit Criticality Benchmark - Phase IV-B Phase IV-B: Results and Analysis of MOX Fuel Depletion Calculations 2003
4331 CINDA 2003 The Index to Literature and Computer Files on Microscopic Neutron Data 2003
3693 International Evaluation Co-operation (Vol. 9) Fission Neutron Spectra of Uranium-235 (Volume 9) 2003
4488 PENELOPE 2003 - A Code System for Monte Carlo Simulation of Electron and Photon Transport Workshop Proceedings, Issy-les-Moulineaux, France, 7-10 June 2003 2003
3038 Physics of Plutonium Recycling - Vol. VII Volume VII: BWR MOX Benchmark - Specification and Results 2003
4451 Plutonium Management in the Medium Term A Review by the OECD/NEA Working Party on the Physics of Plutonium Fuels and Innovative Fuel Cycles (WPPR) 2003
3129 Pressured Water Reactor Main Steam Line Break (MSLB) Benchmark Volume IV: Results of Phase III on Coupled Core-plant Transient Modelling 2003
5188 Research and Development Needs for Current and Future Nuclear Energy Systems (REPRINT) 2003
4310 Utilisation and Reliability of High Power Proton Accelerators Workshop Proceedings, Santa Fe, New Mexico, USA, 12-16 May 2002 2003
3133 A VVER-1000 LEU and MOX Assembly Computational Benchmark Specification and Results 2002
3056 Advanced Reactors with Innovative Fuels Workshop Proceedings, Chester, United Kingdom, 22-24 October 2001 2002
3632 Basic Studies on High-temperature Engineering Second Information Exchange Meeting, Paris, France, 10-12 October 2001 2002
3128 Comparison Calculations for an Accelerator-driven Minor Actinide Burner 2002
3053 Fission Gas Behaviour in Water Reactor Fuels Workshop Proceedings, Cadarache, France, 26-29 September 2000 2002
3209 International Evaluation Co-operation Delayed Neutron Data for the Major Actinides (Volume 6) 2002
3388 PENELOPE 2001 - A Code System for Monte Carlo Simulation of Electron and Photon Transport Workshop Proceedings, Issy-les-Moulineaux, France, 5-7 November 2001 2002
3037 Physics of Plutonium Recycling Multiple Pu Recycling in Advanced PWRs - Volume VI 2002
3117 Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark Volume III: Results of Phase 2 on 3-D Core Boundary Conditions Modelling 2002
3054 Speciation, Techniques and Facilities for Radioactive Materials at Synchroton Light Sources Workshop Proceedings, Grenoble, France, 10-12 September 2000 2002
3055 The Use of Thermodynamic Databases in Performance Assessment Workshop Proceedings, Barcelona, Spain, 29-30 May 2001 2002
4128 VVER-1000 Coolant Transient Benchmark (Vol. I) PHASE 1 (V1000CT-1), Vol. I: Main Coolant Pump (MCP) Switching On - Final Specifications 2002
3115 Boiling Water Reactor Turbine Trip (TT) Benchmark Volume I: Specifications 2001
3168 Evaluation of Speciation Technology Workshop Proceedings, Tokai-mura, Ibaraki, Japan, 26-28 October 1999 2001
3116 Forsmark 1 & 2 Boiling Water Reactor Stability Benchmark Time Series Analysis Methods for Oscillations During BWR Operation: Final Report 2001
3119 International Evaluation Co-operation Evaluation Method of Inelastic Scattering Cross-sections for Weakly Absorbing Fission-product Nuclides (Volume 10) 2001
3328 International Handbook of Evaluated Criticality Safety Benchmark Experiments A Project by the NEA Nuclear Science Committee 2001
3250 International Nuclear Data Evaluation Co-operation Complete Collection of Published Reports as of October 2001 2001
3268 JANIS - A Java-based Nuclear Data Display Program 2001
3488 JANIS Leaflet 2001
3188 Nuclear Production of Hydrogen First Information Exchange Meeting, Paris, France, 2-3 October 2000 2001
2988 Pyrochemical Separations Workshop Proceedings, Avignon, France, 14-16 March 2000 2001
3052 Shielding Aspects of Accelerators, Targets and Irradiation Facilities - SATIF 5 Workshop Proceedings, Paris, France, 18-21 July 2000 2001
3051 Utilisation and Reliability of High Power Proton Accelerators Workshop Proceedings, Aix-en-Provence, France, 22-24 November 1999 2001
2828 3-D Radiation Transport Benchmarks for Simple Geometries with Void Regions 2000
2408 Basic Studies on High-Temperature Engineering First Information Exchange Meeting, Paris, France, 27-29 September 1999 2000
2751 Benchmark Calculations of Power Distribution Within Fuel Assemblies Phase II: Comparison of Data Reduction and Power Reconstruction Methods in Production Codes 2000
2848 Benchmark on the VENUS-2 MOX Core Measurements 2000
2929 CD-CINDA 2000 Index to Literature and Computer Files on Microscopic Neutron Data 2000
2148 Calculations of Different Transmutation Concepts An International Benchmark Exercise 2000
2208 Core Monitoring for Commercial Reactors: Improvements in Systems and Methods Workshop Proceedings, Stockholm, Sweden, 4-5 October 1999 2000
2748 Evaluation and Analysis of Nuclear Resonance Data JEFF Report 18 2000
2749 Evaluation et analyse des données relatives aux résonances nucléaires Rapport JEFF 18 2000
3208 International Evaluation Co-operation Processing and Validation of Intermediate Energy Evaluated Data Files (Volume 14) 2000
2128 Prediction of Neutron Embrittlement in the Reactor Pressure Vessel VENUS-1 and VENUS-3 Benchmarks 2000
2868 Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark Volume II: Results of Phase I on Point Kinetics 2000
2348 The JEF-2.2 Nuclear Data Library JEFF Report 17 2000
1747 Advanced Reactors with Innovative Fuels Workshop Proceedings, Villigen, Switzerland, 21-23 October 1998 1999
4208 Data Bank Leaflet 1999
1988 Intercomparisons of Calculations Made for GODIVA and JEZEBEL JEFF Report 16 1999
1948 International Evaluation Co-operation 238U Capture and Inelastic Cross-Sections (Volume 4) 1999
1907 International Evaluation Co-operation Epithermal Capture Cross-Section of 235U (Volume 18) 1999
1947 International Evaluation Co-operation Present Status of Minor Actinide Data (Volume 8) 1999
1427 Ion and Slow Positron Beam Utilisation Workshop Proceedings, Costa da Caparica, Portugal, 15-17 September 1998 1999
4209 La banque de données (dépliant) 1999
1867 Light Water Reactor (LWR) Pin Cell Benchmark Intercomparisons JEFF Report 15 1999
1467 Physics and Fuel Performance of Reactor-Based Plutonium Disposition Workshop Proceedings, Paris, France, 28-30 September 1998 1999
1587 Pressurised Water Reactor Main Steam Line Break (MSLB) Benchmark Volume I: Final Specifications 1999
1468 Shielding Aspects of Accelerators, Targets and Irradiation Facilities - SATIF 4 Workshop Proceedings, Knoxville, Tennessee, USA, 17-18 September 1998 1999
1727 Speciation, Techniques and Facilities for Radioactive Materials at Synchrotron Light Sources Workshop Proceedings, Grenoble, France, 4-6 October 1998 1999
1627 Utilisation and Reliability of High Power Proton Accelerators Workshop Proceedings, Mito, Japan, 13-15 October 1998 1999
1307 Evaluation of 242Pu Data for the Incident Neutron Energy Range 5-20 MeV 1998
1250 International Evaluation Co-operation Effects of Shape Differences in the Level Densities of Three Formalisms on Calculated Cross-Sections [Volume 16] 1998
1251 International Evaluation Co-operation Status of Pseudo-Fission-Product Cross-Sections for Fast Reactors [Volume 17] 1998
1248 International Evaluation Co-operation Nuclear Models to 200 MeV for High-Energy Data Evaluations [Volume 12] 1998
1249 International Evaluation Co-operation Intermediate Energy Data [Volume 13] 1998
1252 International Nuclear Data Measurement Activities - Newsletter No.3 1998
826 SATIF-3 - Shielding Aspects of Accelerators, Targets and Irradiation Facilities Proceedings of 3rd Specialists Meeting Sendai, Japan, 12-13 May 1997 1998
1247 Thermal Performance of High Burn-Up LWR Fuel Seminar Proceedings, Cadarache, France, 3-6 March 1998 1998
302 Burn-up Credit Criticality Benchmark - Phase IIB 1997
320 Computing Radiation Dose to Reactor Pressure Vessel and Internals State-of-the-art Report 1997
300 Evaluation of Pu-242 1997
347 In-Core Instrumentation and Reactor Core Assessment Proceedings of a Specialist Meeting, Mito-shi, Japan, 16-17 October 1996 1997
305 Intermediate Energy Nuclear Data Benchmark Report 1997
281 International Nuclear Data Measurement Activities - Newsletter No.2 1997
291 Modelling in Aquatic Chemistry 1997
309 Neural Network Benchmark Report 1997
528 Nucleon Nucleus Optical Model up to 200 MeV Proceedings of a Specialist Meeting, Bruyères-le-Châtel, France, 13-15 November 1996 1997
406 PWR Benchmark on Uncontrolled Rods Withdrawal at Zero Power Final Report - September 1997 1997
163 Actinide Separation Chemistry in Nuclear Waste Streams and Materials 1996
1447 Actinide and Fission Product Partitioning and Transmutation Proceedings of the 4th NEA International Information Exchange Meeting, Mito City, Japan, 12-13 December 1996 1996
175 International Evaluation Co-operation Plutonium-239 Fission Cross-section Between 1 and 100 keV [Volume 5] 1996
172 International Evaluation Co-operation Comparison of Evaluated Data for Chromium-52, Iron-56 and Nickel-58 [Volume 1] 1996
174 International Evaluation Co-operation Actinide Data in the Thermal Energy Range [Volume 3] 1996
173 International Evaluation Co-operation Generation of Covariance Files for Iron-56 and Natural Iron [Volume 2] 1996
176 International Evaluation Co-operation Cross-section Fluctuations and Self-shielding Effects in the Unresolved Resonance Region [Volume 15] 1996
217 SMORN-VII Proceedings of the Seventh Symposium on Surveillance and Diagnostics in Nuclear Reactors 1996
216 Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF-2) Proceedings of the Second Specialists' Meeting, Geneva, Switzerland, 12-13 October 1995 1996
164 Advanced Monte Carlo Computer Programs for Radiation Transport Proceedings of a Seminar, Saclay, France, 27-29 April 1993 1995
165 Binding Models Concerning Natural Organic Substances in Performance Assessment Proceedings of an NEA/Paul Scherrer Institute Workshop Bad Zurzach, Switzerland, 14-16 September 1994 1995
1452 Conceptual Design of a Fast Neutron Operated High Power Energy Amplifier 1995 1995
185 International Nuclear Data Measurement Activities - Newsletter No.1 (Revised) 1995
1451 Proceedings of the 8th Journées de SATURNE Saclay, France, 1995 1995
1453 Proceedings of the Second Specialists' Meeting on High Energy Nuclear Data Tokai, Japan, 26-27 January, 1995 1995
197 Review of Nuclear Fuel Experimental Data - Fuel Behaviour Data Available from IFE/OECD Halden Project for Development and Validation of Computer Codes 1995
213 Scientific Issues in Fuel Behaviour 1995
215 Shielding Aspects of Accelerators, Targets and Irradiation Facilities (SATIF-1) Proceedings of the First SATIF Specialists' Meeting Arlington, Texas, U.S.A., 28-29 April 1994 1995
1455 Accelerator-Driven Transmutation Technology The Los Alamos National Laboratory ADTT Update, No.1, July 1994 1994
1448 Actinide and Fission Product Partitioning and Transmutation Proceedings of the 3rd NEA International Information Exchange Meeting, Cadarache, France, 12-14 December 1994 1994
166 Blind Intercomparison of Nuclear Models for Predicting Charged Particle Emission 1994
1457 Hybrid Systems, State of the Art and Prospects 1994 1994
170 Intermediate Energy Nuclear Data: Models and Codes Proceedings of a Specialists' Meeting Issy-les-Moulineaux, France, 30 May-1 June 1994 1994
171 International Code Comparison for Intermediate Energy Nuclear Data 1994
179 JEF Report 13: JEF 2.2 Radioactive Decay Data 1994
180 JEF Report 14: Table of Simple Integral Neutron Cross-section Data from JEF-2.2, ENDF/B-VI, JENDL-3.2, BROND-2 and CENDL-2 1994
186 NJOY and THEMIS Nuclear Data Proceedings of a Seminar Saclay, France, 7-8 April 1992 1994
1456 Overview of Physics Aspects of Different Transmutation Concepts NSC/DOC(94)24, 1994 1994
233 Sensitivities of Calculated Cross-section of Fe56 to Model Parameters 1994
218 Summary of the Work of the NEANDC Task Force on U-238 1994
1458 Transmutation of Fission Products in Reactors and Accelerator-Driven Systems Some critical remarks, January 1994 1994
167 Evaluation and Processing of Covariance Data Proceedings of a Specialists' Meeting Oak Ridge National Laboratory, U.S.A., 7-9 October 1992 1993
1459 Extracts from the Proceedings of the Global' 93 Conference Seattle, USA, 1993 1993
196 Results of LWR Core Transient Benchmarks 1993
161 Strategic View on Nuclear Data Needs 1993
1449 Actinide and Fission Product Partitioning and Transmutation Proceedings of the 2nd NEA International Information Exchange Meeting, Argonne, USA, 11-13 November 1992 1992
159 Data Bank (The) - Putting Nuclear Data to Work 1992
169 Fission Product Nuclear Data Proceedings of a Specialists' Meeting Tokai, Japan, May 1992 1992
1454 Impacts of New Developments in Partitioning and Transmutation on the Disposal of High-level Nuclear Waste in a Mined Geologic Repository February, 1992 1992
187 Nuclear Data Standards for Nuclear Measurements - 1991 Nuclear Standards File 1992
1460 Proceedings of the Specialist Meeting on Accelerator Based Transmutation Villigen, Switzerland, 1992 1992
1461 Review of High Energy Data and Model Codes for Accelerator-Based Transmutation NSC/DOC(92)12 - P&T Report No.4, NEA/OECD, 1992 1992
1887 Advanced Modelling and Computer Codes for Calculating Local Scale and Meso-Scale Atmospheric Dispersion of Radionuclides and their Applications Proceedings of the Specialists' Meeting 6-8 March 1991 1991
1832 In Core Instrumentation and Reactor Assessment Proceedings of a Specialist' Meeting Pittsburg, USA, 1-4 October 1991 1991
182 Neutron Cross-section Standards for the Energy Region Above 20 MeV Proceedings of a Specialists' Meeting, Uppsala, Sweden, May 1991 1991
1462 Role and Influence of Partitioning and Transmutation 1991
1463 Survey of Codes Relevant to Design, Engineering and Simulation of Tranmutation of Actinide by Spallation 1991
1838 Symposium on nuclear Reactor surveillance and Diagnostics - SMORN VI Proceedings of a Specialists' Meeting Gatlinburg, Tennessee, USA, 19-24 May 1991 1991
1450 Actinide and Fission Product Partitioning and Transmutation Proceedings of the 1st NEA International Information Exchange Meeting, Miso City, Japan, 6-8 November 1990 1990
1888 PSACOIN Level 1A Intercomparison An International Code Intercomparison Exercise on a Hypothetical Safety Assessment Case Study for Radioactive Waste Disposal Systems 1990
1892 PSACOIN Level E Intercomparison An International Code Intercomparison Exercise on a Hypothetical Safety Assessment Case Study for Radioactive Waste Disposal Systems 1989
1831 In Core Instrumetation and Reactor Assessment Proceedings of a Specialists' Meeting Cadarache, France, 7-10 June 1988 1988
1891 PSACOIN Level 0 Intercomparison An International Code Intercomparison Exercise on a Hypothetical Safety Assessment Case Study for Radioactive Waste Disposal Systems 1987
1837 Reactor Noise - SMORN V Proceedings of a Specialists' Meeting Munich, FRG, 12-16 October 1987 1987
1836 Reactor Noise - SMORN IV Proceedings of a Specialists' Meeting Dijon, France, 15-19 October 1984 1984
1829 In Core Instrumentation and Reactor Assessment Proceedings of a Secialists' Meeting Fredrikstad, Norway, 10-13 October 1983 1983
1827 Nuclear Data and Benchmarks for Reactor Shielding Proceedings of a Specialist' Meeting Paris, 27-29 October 1980 1981
1835 Reactor Noise - SMORN III Proceedings of a Specialists' Meeting Tokyo, Japan, 26-30 October 1981 1981
1828 Calculation of 3-Dimensional Rating Distributions in Operating Reactors Proceedings of a Specialists' Meeting Paris, 26-28 November 1979 1979
1834 Reactor Noise - SMORN II Proceedings of a Specialists' Meeting Gatlinburg, Tennessee, USAm 19-23 September 1977 1977
1833 Reactor Noise - SMORN I Proceedings of a Specialists' Meeting CSN Casaccia, Rome, Italy, 21-25 October 1974 1974