N. Aksan - Concepedia

Author

N. Aksan

Commissariat à l'Énergie Atomique et aux Énergies Alternatives ORCID

Also Known As

AKSAN Nusret, Aksan, Nusret, N Aksan, N. Aksan, Nusret Aksan

Publications

638

Citations

H-Index

Concepts

All Affiliations

Commissariat à l'Énergie Atomique et aux Énergies Alternatives University of Pisa VTT Technical Research Centre of Finland Korea Atomic Energy Research Institute Gesellschaft für Anlagen und Reaktorsicherheit

About

N. Aksan is an author at Commissariat à l'Énergie Atomique et aux Énergies Alternatives specializing in engineering, nuclear engineering, and heat transfer.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	10	12	505
2	Civil Engineering	2	2	66
3	Computer Science	2	2	27
4	Chemical Engineering	1	1	146
5	Computer Engineering	1	1	24

N. Aksan

Publications

570

Citations

H-Index

Page 1

	Year	Citations
High performance light water reactor D. Squarer, Thomas S. Schulenberg, D. Struwe, Nuclear Engineering and Design Chemical EngineeringEngineeringEnergy EfficiencyReactor DesignWater Treatment	2003	146
Passive Safety Systems and Natural Circulation in Water Cooled Nuclear Power Plants N. Aksan, J.H. Choi, Y.G. Chung, Passive Safety SystemsEngineeringNuclear EngineeringNuclear SafetyNatural Circulation	2009	122
Issues and future direction of thermal-hydraulics research and development in nuclear power reactors Pradip Kumar Saha, N. Aksan, Jacob Andersen, Nuclear Engineering and Design Core Thermal HydraulicsEngineeringThermal-hydraulics ResearchThermal HydraulicsReactor Design	2013	46
Thermal-hydraulic phenomena for water cooled nuclear reactors N. Aksan, Francesco Saverio D'Auria, H. Glaeser Nuclear Engineering and Design Core Thermal HydraulicsEngineeringThermal HydraulicsAlwr Thermal HydraulicsThermodynamics	2018	38
Thermohydraulic Relationships for Advanced Water Cooled Reactors N. Aksan, Francesco Saverio D'Auria, D.C. Groeneveld, EngineeringThermal HydraulicsThermophysicsThermodynamicsHeat Transfer	2001	34
Natural Circulation Phenomena and Modelling for Advanced Water Cooled Reactors N. Aksan, Bolado Lavin Ricardo, L. Burgazzi, IAEA eBooks	2012	34
Heat Transfer Behaviour and Thermohydraulics Code Testing for Supercritical Water Cooled Reactors (SCWRs) N. Aksan, Walter Ambrosini, Luca Ammirabile, International Atomic Energy Agency eBooks	2014	31
International Standard Problems and Small Break Loss-of-Coolant Accident (SBLOCA) N. Aksan Science and Technology of Nuclear Installations EngineeringReactor DesignSafety ScienceCode CapabilitiesNuclear Reactor Design	2008	24
FONESYS: The FOrum & NEtwork of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics Seung-Hoon Ahn, N. Aksan, H. Austregesilo, Nuclear Engineering and Design Thermodynamic ModellingSystem Thermal-hydraulic CodesCore Thermal HydraulicsEngineeringNuclear Reactor Thermal-hydraulics	2014	20
An overview on thermal-hydraulic phenomena for water cooled nuclear reactors; part I: SETs, and ITFs of PWRs, BWRs, VVERs N. Aksan Nuclear Engineering and Design Core Thermal HydraulicsEngineeringThermal HydraulicsNuclear ReactorsCivil Engineering	2019	20

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