7499 |
Chemical Thermodynamics of Iron – Part 2 |
2020 |
7520 |
International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook 2020 |
2020 |
7519 |
Specifications for the Generalised Nuclear Database Structure (GNDS) |
2020 |
7498 |
International Co-operation in Nuclear Data Evaluation An Extended Summary of the Collaborative International Evaluated Library Organisation (CIELO) Pilot Project |
2019 |
7497 |
International Handbook of Evaluated Criticality Safety Benchmark Experiments – 2019 |
2019 |
7496 |
International Handbook of Evaluated Reactor Physics Benchmark Experiments – 2019 |
2019 |
7513 |
Knowledge management in the context of an ageing workforce NEA Policy Brief |
2019 |
7500 |
Second Update on the Chemical Thermodynamics of Uranium, Neptunium, Plutonium, Americium and Technetium |
2019 |
7511 |
Thermal Scattering Law S(α,β): Measurement, Evaluation and Application International Evaluation Co-operation Volume 42 |
2019 |
7360 |
International Handbook of Evaluated Criticality Safety Benchmark Experiments – DVD |
2018 |
7361 |
International Handbook of Evaluated Reactor Physics Benchmark Experiments – DVD |
2018 |
7317 |
State-of-the-Art Report on Light Water Reactor Accident-Tolerant Fuels |
2018 |
7267 |
State-of-the-art Report on the Progress of 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 |
7133 |
Transition Towards a Sustainable Nuclear Fuel Cycle |
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 |
7042 |
Assessment of the Unresolved Resonance Treatment for Cross-section and Covariance Representation International Evaluation Co-operation, Volume 32 |
2011 |
7040 |
Covariance Data in the Fast Neutron Region International Evaluation Co-operation, Volume 24 |
2011 |
6894 |
Potential Benefits and Impacts of Advanced Nuclear Fuel Cycles with Actinide Partitioning and Transmutation |
2011 |
7041 |
Quality Improvement of the EXFOR Database International Evaluation Co-operation, Volume 30 |
2011 |
6897 |
Technology and Components of Accelerator-driven Systems Workshop Proceedings, Karlsruhe, Germany, 15-17 March 2010 |
2011 |
7043 |
Uranium-235 Capture Cross-section in the keV to MeV Energy Region International Evaluation Co-operation, Volume 29 |
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 |
6941 |
JEFF Reports CD-ROM Complete Collection of JEFF Reports 1-22 |
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 |
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 |
7451 |
铅与铅铋共晶合金手册性能、材料相容性、热工水力学和技术 - 2007版 Handbook on Lead-bismuth Eutectic Alloy and Lead Properties, Materials Compatibility, Thermal-hydraulics and Technologies - 2007 Edition (Chinese version) |
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 |
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 |
3114 |
Chemical Thermodynamics of Neptunium and Plutonium (Volume 4) Published by Elsevier |
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 |
1947 |
International Evaluation Co-operation Present Status of Minor Actinide Data (Volume 8) |
1999 |
1907 |
International Evaluation Co-operation Epithermal Capture Cross-Section of 235U (Volume 18) |
1999 |
1948 |
International Evaluation Co-operation 238U Capture and Inelastic Cross-Sections (Volume 4) |
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 |
1248 |
International Evaluation Co-operation Nuclear Models to 200 MeV for High-Energy Data Evaluations [Volume 12] |
1998 |
1251 |
International Evaluation Co-operation Status of Pseudo-Fission-Product Cross-Sections for Fast Reactors [Volume 17] |
1998 |
1250 |
International Evaluation Co-operation Effects of Shape Differences in the Level Densities of Three Formalisms on Calculated Cross-Sections [Volume 16] |
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 |
176 |
International Evaluation Co-operation Cross-section Fluctuations and Self-shielding Effects in the Unresolved Resonance Region [Volume 15] |
1996 |
172 |
International Evaluation Co-operation Comparison of Evaluated Data for Chromium-52, Iron-56 and Nickel-58 [Volume 1] |
1996 |
173 |
International Evaluation Co-operation Generation of Covariance Files for Iron-56 and Natural Iron [Volume 2] |
1996 |
174 |
International Evaluation Co-operation Actinide Data in the Thermal Energy Range [Volume 3] |
1996 |
175 |
International Evaluation Co-operation Plutonium-239 Fission Cross-section Between 1 and 100 keV [Volume 5] |
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 |
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 |
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 |