| NEA/CNRA/R(2017)1 | First Triennial Report of the WGIP Benchmarking on Inspection Practices |
| NEA/CNRA/R(2017)2 | Report on the Survey of the Design Review of New Reactor Applications - Volume 5: Classification of Structures, Systems, and Components |
| NEA/CNRA/R(2017)3 | Report on the Survey of the Regulatory Practice to Assess Passive Safety Systems Used in New Nuclear Power Plant Designs First Stage Report |
| NEA/CNRA/R(2017)4 | Operational Experience from Heavy Load Incidents |
| NEA/CNRA/R(2017)6 | Nuclear Regulatory Organisations' Oversight of New Licensee Organisational Capability - Workshop Proceedings, Chester, United Kingdom, March 2017 |
| NEA/CNRA/R(2017)6/ADD1 | Nuclear Regulatory Organisations' Oversight of New Licensee Organisational Capability - Workshop Proceedings, Chester, United Kingdom, March 2017 - Appendices
|
| NEA/CNRA/R(2017)7 | A Comprehensive Report on Three Regional Stakeholder
Workshops in Europe, North America and Asia |
| NEA/CNRA/R(2017)8 | Regulatory Oversight of the Commissioning Phase for New
Nuclear Reactors:
Proceedings of the Joint CNRA WGRNR/MDEP Workshop Republic of Korea 14-16 March 2016
|
| NEA/CSNI/R(2017)1 | Reactivity-Initiated Accident (RIA) Fuel-Codes Benchmark Phase II: Uncertainty and Sensitivity Analyses |
| NEA/CSNI/R(2017)2 | Proceedings of the Fourth International Conference on Fatigue of Nuclear Reactor Components
28th September-1 October 2015 in Seville, Spain |
| NEA/CSNI/R(2017)2/ADD1 | APPENDIX 4 - Proceedings of the 4th International Conference on Fatigue of Nuclear Reactor Components
28 September-1 October 2015
Seville, Spain |
| NEA/CSNI/R(2017)3 | Operating Experience Insights into Pressure Boundary Component Reliability and Integrity Management -
Topical Report by the Component Operational Experience, Degradation and Ageing Programme (CODAP) Group
|
| NEA/CSNI/R(2017)4 | The Safety of Long-Term Interim Storage Facilities in NEA member countries |
| NEA/CSNI/R(2017)5 | Probabilistic Safety Assessment Insights Relating to the Loss of Electrical Sources |
| NEA/CSNI/R(2017)6 | Project Solving Thermal Hydraulic Safety Issues for Current and New Pressurised Water Reactor Design Concepts
Primary Coolant Loop Test Facility (PKL2) Project - Final Report |
| NEA/CSNI/R(2017)7 | Report on the Testing Phase
(2014-2016) of the High Energy Arcing Fault Events (HEAF) Project: Experimental Results from
the International Energy Arcing
Fault Research Programme |
| NEA/CSNI/R(2017)8 | ICDE Project Report: ICDE Workshop - Collection and Analysis of Emergency Diesel Generator Common-Cause Failures Impacting Entire Exposed Population |
| NEA/CSNI/R(2017)9 | Summary Report of the NEA-Advanced Thermal-Hydraulic Test
Loop for Accident Simulation (ATLAS) Joint Project |
| NEA/CSNI/R(2017)10 | Summary and Conclusions of the Joint PKL-3-ATLAS Workshop
on Analytical Activities
Lucca, Italy
13-15 April 2016 |
| NEA/CSNI/R(2017)11 | Benchmark Results on the Analytical Evaluation of the Fracture Mechanic Parameters K and J |
| NEA/CSNI/R(2017)12 | Proceedings of the CSNI Workshop on Developments in Fuel Cycle Facilities (FCFs) after the Fukushima Daiichi Nuclear Power Station (NPS) Accident
Aomori City, Japan, 15-17 November 2016 |
| NEA/CSNI/R(2017)12/ADD1 | APPENDIX 3 - CONFERENCE PAPERS
Proceedings of the CSNI Workshop on Developments in Fuel Cycle Facilities (FCFs) after the Fukushima Daiichi Nuclear Power Station (NPS)Accident
Aomori City, Japan
15-17 November 2016
|
| NEA/CSNI/R(2017)13 | Workshop Proceedings -Working Group on External Events (WGEV)
Understanding the Impact of External Hazards on Nuclear Facilities: Severe Weather and Storm Surge
Paris, France, 24-26 February 2016
|
| NEA/CSNI/R(2017)14 | Investigating Heat and Smoke Propagation Mechanisms in Multi-Compartment Fire Scenarios: Final Report of the PRISME Project |
| NEA/CSNI/R(2017)15 | Status Report on Ex-Vessel Steam Explosion: EVSE |
| NEA/CSNI/R(2017)16 | Informing Severe Accident Management Guidance and Actions for Nuclear Power Plants through Analytical Simulation |
| NEA/CSNI/R(2017)17/REV1 | Operating Plan and Guidelines for the Nuclear Energy Agency Committee on the Safety of Nuclear Installations: 2017-2022 |
| NEA/CSNI/R(2017)18 | Phenomena Identification and
Ranking Table (PIRT) on Spent Fuel Pools under Loss-of-Cooling and Loss-of-Coolant Accident Conditions
WGFS Report |
| NEA/CSNI/R(2017)19 | OECD/NEA CFD–UQ Benchmark Exercise:
CFD prediction and Uncertainty Quantification of a GEMIX mixing layer test
|
| NEA/CSNI/R(2017)20 | Computational Fluid Dynamics for Nuclear Reactor Safety Applications-6(CFD4NRS-6)
Workshop Proceedings
13-15 September 2016
Cambridge USA |
