| Download Link |
Title |
| All Papers in a Zip |
Compressed zip file containing all papers (From A0002 to A0093) |
| |
|
| TopSafe2017-A0002 |
Retrofitting of passive safety systems for plant life-time extension |
| TopSafe2017-A0003 |
Integrated systems and tools for repeatable nuclear knowledge management & operating experience implemented at the university of utah nuclear research reactor facility |
| TopSafe2017-A0004 |
Development of defence-in-depth evaluation method against external events |
TopSafe2017-A0006
|
Eniss contribution to the harmonisation of the regulatory framework |
TopSafe2017-A0008
|
Effectiveness of Depressurization and Injections Strategies during Extended SBO for BWRs |
| TopSafe2017-A0009 |
Development of organic iodine adsorbents |
TopSafe2017-A0010
|
The Role of IAEA in Human Capacity Building - Active Learning and Training-by-Doing Education Programmes Based on the Basic Principle Reactor Simulators |
| TopSafe2017-A0011 |
Design for protection against external events in Tepco's Kashiwazaki-Kariwa Nuclear Power Station |
TopSafe2017-A0012
|
Decommissioning and Environmental Remediation Scenario Development for Fukushima Daiichi |
TopSafe2017-A0013
|
Analysis of Eutectic and Metallic Melt Flow and Blockage in BWR Control Rod Guide Tube by MPS Method |
TopSafe2017-A0014
|
BEPU-FSAR: A new paradigm in Nuclear Reactor Safety |
TopSafe2017-A0015
|
JANSI's Safety Improvement Activities with IAEA SRS-46 |
TopSafe2017-A0016
|
The Improvement of Downcomer and Lower-Plenum Model of Chinshan Nuclear Power Plant by Using CFD Simulation |
TopSafe2017-A0018
|
Lessons Learnt from the UK Generic Design Assessment Process |
TopSafe2017-A0021
|
Novel Approach to Improved Concrete Strength for Enhanced Safety and Durability of the Nuclear Power Plant Operation |
| TopSafe2017-A0022 |
Development of a new seismic PRA code for uncertainty analysis |
TopSafe2017-A0023
|
Present Situation and Trends of Nuclear Power in Japan after Fukushima Accident |
TopSafe2017-A0024
|
Analysis of an postulated ELAP event in Maanshan NPP using TRACE code |
TopSafe2017-A0025
|
Enhance Nuclear Safety and Reliability of Nuclear Power Plants through Human Resource Development |
TopSafe2017-A0026
|
Features of the radial reflector simulation for generation of two-group xs for the vver reactor core in serpent monte carlo code |
| TopSafe2017-A0027 |
Trends in severe accident research in Europe: SARNET network from Euratom to NUGENIA |
| TopSafe2017-A0028 |
Safety and Standardization Issues on ISO12100 of Safety Design and Operation Principle for Nuclear Power Plants |
| TopSafe2017-A0029 |
An Assessment on the Stability Performance of a PWR with ATF |
TopSafe2017-A0030
|
Severe Accident Consequence Assessment for Chinshan NPP in Taiwan Using MELCOR2.1 and WinMACCS |
| TopSafe2017-A0031 |
International database on heavy water reactor pressure tube diametral creep |
| TopSafe2017-A0032 |
Thermal Hydraulic Analysis on the Transient Phenomena in the Pressure Balancing Line of the Hybrid Safety Injection Tank |
| TopSafe2017-A0034 |
IAEA Collaborations on Advancing Water Cooled Reactor Technologies |
| TopSafe2017-A0036 |
Fractionated dosage of hydrogenated additives in UO2 powder blending process |
| TopSafe2017-A0037 |
University of Utah Nuclear Engineering Program’s Metamorphosis of Public Perception of Nuclear Energy |
TopSafe2017-A0038
|
Enusa-Juzbado plant stress test approach and actions taken |
TopSafe2017-A0040
|
Views on Defence in Depth implementation |
TopSafe2017-A0042
|
Managing Nuclear Power Plant Safety with FeCrAl Alloy Fuel Cladding |
TopSafe2017-A0044
|
Development and Preliminary Application of the Methodologies for Evaluating Severe Accident Management Program |
TopSafe2017-A0045
|
RELAP/SCDAPSIM/MOD 3.5. analysis of KIT’s QUENCH-14 experiment using M5® Cladding Material |
TopSafe2017-A0046
|
Development of a CANDU-6 plant model using grape |
TopSafe2017-A0048
|
Identification of thermal-hydraulic phenomena for validation of best-estimate computer codes |
TopSafe2017-A0050
|
On the role of the safety analysis in the plant life extension strategy |
TopSafe2017-A0051
|
Analysis of Molten-Corium Concrete Interaction for Small Modular Reactor |
TopSafe2017-A0052
|
Decision Making Methodology of Cost-benefit Analysis Based on Probabilistic Safety Assessment for Accident Mitigation Alternatives |
| TopSafe2017-A0053 |
Re-assessment of RELAP/SCDAPSIM/MOD3.x using Historical Integral Experiments |
| TopSafe2017-A0054 |
Management of nuclear safety and security synergy |
TopSafe2017-A0056
|
Numerical investigation of the recriticality of the molten corium based on heavy metals during severe accident in light water reactor |
TopSafe2017-A0058
|
In Vessel Melt Retention Strategy( IVMR) for VVER 1000 – Status of Work |
| TopSafe2017-A0062 |
Defence in Depth and practical elimination of early and large releases – concepts and practice. |
| TopSafe2017-A0063 |
The BR2 matrix replacement and safety upgrades. |
TopSafe2017-A0064
|
Applying Probabilistic Concepts in External Flooding Applications at Nuclear Power Plants |
TopSafe2017-A0070
|
Defence in depth internalization in carem prototype and basis for safety classification of structures systems and components |
| TopSafe2017-A0071 |
ATWS control by a Boron Injection System in CAREM-25 |
| TopSafe2017-A0072 |
Ongoing activities of the working group on accident management and analysis (csni/wgama) |
TopSafe2017-A0075
|
Severe NPP Accident Management by Integrated Drone-Based Monitoring System |
TopSafe2017-A0076
|
The path towards a germane safety and licensing approach for modular high temperature gas-cooled reactors |
| TopSafe2017-A0077 |
Has Japan Overcome the Impact of Fukushima?: interaction between the government and the civil society over nuclear safety issues |
TopSafe2017-A0078
|
The Five Essential Elements of Severe Accident Management - to be Developed as Part of an Industry Standard |
TopSafe2017-A0079
|
Performance Evaluation of Safety Injection Tank for APR1400 Plant |
| TopSafe2017-A0080 |
Regulatory Considerations on Site Release of Nuclear Facilities after the Completion of Decommissioning |
| TopSafe2017-A0081 |
Westinghouse experience on Aging Management in the Nordic region and general overview of the methodology |
| TopSafe2017-A0082 |
The journey to a certified Equipment Qualification laboratory – Westinghouse approach and lessons learned |
| TopSafe2017-A0084 |
Ageing Management and Long Term Operation in VVER440 |
TopSafe2017-A0085
|
Cask thermal analysis to assess spent fuel safety: from the CFD modelling to the engineering approach |
TopSafe2017-A0086
|
Independent assessment for new nuclear reactor safety |
| TopSafe2017-A0088 |
Simplified High Winds Risk Assessments |
| TopSafe2017-A0089 |
AP1000® Plant United Kingdom Generic Design Assessment (GDA) Closeout Efforts |
TopSafe2017-A0090
|
Strategic Refurbishment Program for Reactor Coolant Pumps and Motors |
TopSafe2017-A0091
|
Reactor Coolant Pump Seal Enhancements Including Post-Fukushima Solutions |
TopSafe2017-A0093
|
Preparation of Rock for Supporting a Nuclear Power Plant Foundation |
