| NEA/CNRA/R(2016)1 | Report on the Survey of the Design Review of New Reactor Applications - Volume 3: Reactor |
| NEA/CNRA/R(2016)2 | 13th International Nuclear Regulatory Inspection Workshop |
| NEA/CNRA/R(2016)2/ADD1 | 13th International Nuclear Regulatory Inspection Workshop + Appendix |
| NEA/CNRA/R(2016)3 | Report on the Survey of the Design Review of New Reactor Applications - Volume 4: Reactor Coolant and Associated Systems
|
| NEA/CSNI/R(2016)1 | Computational Fluid Dynamics for Nuclear Reactor Safety-5 (CFD4NRS-5) - Workshop Proceedings, 9-11 September 2014, Zurich, Switzerland |
| NEA/CSNI/R(2016)2 | The Nuclear Energy Agency/Paul Scherrer Institute Computational Fluid Dynamics Benchmark Exercise |
| NEA/CSNI/R(2016)3 | Proceedings of an OECD/CSNI Workshop on Operational and Regulatory Aspects of Criticality Safety
|
| NEA/CSNI/R(2016)4 | Review of Uncertainty Methods for Computational Fluid Dynamics Application to Nuclear Reactor Thermal Hydraulics |
| NEA/CSNI/R(2016)5 | International Iodine Workshop Summary Report |
| NEA/CSNI/R(2016)6/VOL1 | Reactivity Initiated Accident (RIA) Fuel Codes Benchmark Phase-II
Volume 1:
Simplified Cases Results
Summary and Analysis
|
| NEA/CSNI/R(2016)6/VOL2 | Reactivity Initiated Accident (RIA) Fuel Codes Benchmark Phase-II
Volume 2: Task No. 1 Specifications |
| NEA/CSNI/R(2016)7 | OECD FIRE Report - Topical Report n°3
Event Combinations of Fires and Other Events |
| NEA/CSNI/R(2016)8 | Aerosol and Iodine Issues, and Hydrogen Mitigation under Accidental Conditions in Water Cooled Reactors -
Thermal-hydraulics, Hydrogen, Aerosols and Iodine (THAI-2) Project -
Final Report |
| NEA/CSNI/R(2016)9 | PREMIUM: A Benchmark on the Quantification of the Uncertainty of the Physical Models in the System Thermal-Hydraulic Codes - Methodologies and Data Review |
| NEA/CSNI/R(2016)10 | Final Integration Report of the Rig-of-safety Assessment (ROSA-2) Project - 2009-2012 |
| NEA/CSNI/R(2016)11 | Results of questionnaire on Buried and Underground Tanks and Piping |
| NEA/CSNI/R(2016)12 | Probabilistic Structural Integrity of a Pressurised Water Reactor (PWR) Pressured Vessel - Final Report |
| NEA/CSNI/R(2016)13 | Final Report on the Phase 1 of the Assessment of Structures Subjected to Concrete Pathologies (ASCET) |
| NEA/CSNI/R(2016)13/ADD1 | Final Report on the Phase 1 of the Assessment of Structures Subjected to Concrete Pathologies (ASCET) – APPENDICES |
| NEA/CSNI/R(2016)14 | Scaling in System Thermal-Hydraulics Applications to Nuclear Reactor Safety and Design: a State-of-the-Art Report. |
| NEA/CSNI/R(2016)15 | State-of-the-Art Report on Molten-Corium-Concrete interaction and Ex-Vessel Molten-Core Coolability |
| NEA/CSNI/R(2016)16 | REPORT ON FUEL FRAGMENTATION, RELOCATION, DISPERSAL (FFRD) |
| NEA/CSNI/R(2016)17 | Experts' Workshop On Human Factors Validation of Nuclear Power Plant Control Room Designs and Modifications - February 19-21, 2015
Charlotte, North Carolina (USA)
|
| NEA/CSNI/R(2016)17/ADD1 | Human Factors Validation of Nuclear Power Plant Control Room Designs
and Modifications
Proceedings of the Expert Workshop
Charlotte, United States
19-21 February 2015
APPENDIX B White Papers |
| NEA/CSNI/R(2016)17/ADD2 | Human Factors Validation of Nuclear Power Plant Control Room Designs
and Modifications
Proceedings of the Expert Workshop
Charlotte, United States
19-21 February 2015
APPENDIX C Speaker presentations: abstracts/texts graphics |
| NEA/CSNI/R(2016)18 | Post-BEMUSE Reflood Model Input Uncertainty Methods (PREMIUM) Benchmark
Final Report |
| NEA/CSNI/R(2016)19 | Safety Research Opportunities Post-Fukushima -
Initial Report of the Senior Expert Group |
| NEA/SEN/SIN/IAGE/A(2016)1 | 38th MEETING OF THE INTEGRITY AND AGEING OF COMPONENTS AND STRUCTURES WORKING GROUP (WGIAGE)
|
| NEA/SEN/SIN/WGRISK/A(2016)1 | 17th Meeting of the Working Group on Risk Assessment |
