Ali Abou-Sena

Dr. Ali Abou-Sena

orcid

Research Focus & Metrics

Academic Career Length

24Years (2003-Present)

(Calculated once Scilit publication data is synced: current year − year of first publication + 1)

Representative Publications

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22 July 2015 in Nuclear Fusion
Verified
Journal Article
Closed access
JKJ. Knaster
J. Knaster
AIA. Ibarra
A. Ibarra
JAJ. Abal
J. Abal
AAAli Abou-Sena
Ali Abou-Sena
FAF. Arbeiter
F. Arbeiter
TYT. Yokomine
T. Yokomine

1 May 2005 in Fusion Science and Technology
Verified
Journal Article
Closed access
AAAli Abou-Sena
Ali Abou-Sena
AYA. Ying
A. Ying
MAM. Abdou
M. Abdou
The use of lithium ceramic pebble beds has been considered in many blanket designs for the fusion reactors. Lithium ceramics have received a significant interest as tritium breeders for the fusion blankets during the last three decades. The thermal performance of the lithium ceramic pebble beds plays a key role for the fusion blankets. In order to study the heat transfer in the blanket, the effective thermal conductivity of the lithium ceramics pebble beds has to be well measured and characterized. The data of effective thermal conductivity of lithium ceramic pebble beds is important for the blanket design. Several studies have been dedicated to investigate the effective conductivity of the lithium ceramics pebble beds. The objective of this work is to review and compare the available data, presented by various studies, of effective conductivity of lithium ceramic pebble beds in order to address the current status of these data.

1 January 2007 in Journal of Materials Processing Technology
Verified
Journal Article
Closed access
AAAli Abou-Sena
Ali Abou-Sena
AYAlice Ying
Alice Ying
MAMohamed Abdou
Mohamed Abdou

1 December 2016 in Nuclear Materials and Energy
Verified
Journal Article
Open access
FAF. Arbeiter
F. Arbeiter
AAAli Abou-Sena
Ali Abou-Sena
JAJ. Averhals
J. Averhals
TBT. Böttcher
T. Böttcher
YCY. Chen
Y. Chen
KZK. Zinn
K. Zinn
During the Engineering Validation and Engineering Design Activities (EVEDA) phase (2007-2014) of the International Fusion Materials Irradiation Facility (IFMIF), an advanced engineering design of the High Flux Test Module (HFTM) has been developed with the objective to facilitate the controlled irradiation of steel samples in the high flux area directly behind the IFMIF neutron source. The development process addressed included manufacturing techniques, CAD, neutronic, thermal-hydraulic and mechanical analyses complemented by a series of validation activities. Validation included manufacturing of 1:1 parts and mockups, test of prototypes in the FLEX and HELOKA-LP helium loops of KIT for verification of the thermal and mechanical properties, and irradiation of specimen filled capsule prototypes in the BR2 test reactor. The prototyping activities were backed by several R&D studies addressing focused issues like handling of liquid NaK (as filling medium) and insertion of Small Specimen Test Technique (SSTT) specimens into the irradiation capsules. This paper provides an up-todate design description of the HFTM irradiation device, and reports on the achieved performance criteria related to the requirements. Results of the validation activities are accounted for and the most important issues for further development are identified

1 October 2013 in Fusion Engineering and Design
Verified
Journal Article
Closed access
JRJoerg Reimann
Joerg Reimann
AAAli Abou-Sena
Ali Abou-Sena
RNRainer Nippen
Rainer Nippen
PTPaul Tafforeau
Paul Tafforeau

31 October 2011 in Fusion Engineering and Design
Verified
Journal Article
Closed access
FAFrederik Arbeiter
Frederik Arbeiter
AAAli Abou-Sena
Ali Abou-Sena
YCYuming Chen
Yuming Chen
BDBernhard Dolensky
Bernhard Dolensky
THTobias Heupel
Tobias Heupel
GSGeorg Schlindwein
Georg Schlindwein