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S. Sharafat
Observed name:
S Sharafat
Observed institutions:
University of California, Los Angeles,
Rensselaer Polytechnic Institute,
General Atomics (United States)
OpenAlex ID:
A5021350482
Economic, safety and environmental prospects of fusion reactors
1990
·
R.W. Conn
, J.P. Holdren
, et al.
·
Nuclear Fusion
·
49
The Aries-i Tokamak Reactor Study
1991
·
F. Najmabadi
, R.W. Conn
, et al.
·
Elsevier eBooks
·
46
The ARIES-II and ARIES-IV Second-Stability Tokamak Reactors
1992
·
F. Najmabadi
, R. W. Conn
, et al.
·
Fusion Technology
·
35
The ARIES-III D-3He tokamak-reactor study
2002
·
F. Najmabadi
, R.W. Conn
, et al.
·
IEEE/NPSS Symposium on Fusion Engineering
·
17
ARIES-I SiC Composite Low Activation Blanket Design
1991
·
C.P.C. Wong
, E. T. Cheng
, et al.
·
Fusion Technology
·
11
Thermodynamic stability of oxide, nitride, and carbide coating materials in liquid Sn–25Li
2004
·
S Sharafat
, N Ghoniem
, et al.
·
Journal of Nuclear Materials
·
10
Blanket design for the ARIES-I tokamak reactor
2003
·
C.P.C. Wong
, E.T. Cheng
, et al.
·
IEEE/NPSS Symposium on Fusion Engineering
·
9
PDF
Design and analysis of the Prometheus wetted wall IFE reactor cavity
2002
·
M.S. Tillack
, M.Z. Youssef
, et al.
·
IEEE/NPSS Symposium on Fusion Engineering
·
7
Design layout and maintenance of the ARIES-III tokamak reactor
2002
·
S. Sharafat
, F. Najmabadi
, et al.
·
IEEE/NPSS Symposium on Fusion Engineering
·
6
Design layout and maintenance of the ARIES-IV tokamak fusion power plant
2002
·
S. Sharafat
, R. Junge
, et al.
·
IEEE/NPSS Symposium on Fusion Engineering
·
5
ARIES-IV Nested Shell Blanket design
2002
·
C.P.C. Wong
, K. Redler
, et al.
·
IEEE/NPSS Symposium on Fusion Engineering
·
4
PDF
Material selection for the titan reversed-field pinch reactor
1989
·
S. Sharafat
, N.M. Ghoniem
, et al.
·
Fusion Engineering and Design
·
4
Engineering and geometric aspects of the solid wall re-circulating fluid blanket based on advanced ferritic steel
2004
·
I.N. Sviatoslavsky
, M.E. Sawan
, et al.
·
Fusion Engineering and Design
·
3
ARIES-III divertor engineering design
1992
·
C.P.C. Wong
, Kenneth R. Schultz
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
3
PDF
Overview of the titan-II reversed-field pinch aqueous fusion power core design
1989
·
C.P.C. Wong
, R.L. Creedon
, et al.
·
Fusion Engineering and Design
·
3
Proposed damage evolution model for large-scale finite element modeling of the dual coolant US-ITER TBM
2007
·
S. Sharafat
, J. El-Awady
, et al.
·
Journal of Nuclear Materials
·
1
Silicon-carbide composite materials for the ARIES-I reactor study
2003
·
S. Sharafat
, N.M. Ghoniem
, et al.
·
IEEE/NPSS Symposium on Fusion Engineering
·
1
Thermo-structural design of the ARIES-III divertor with organic coolant in subcooled flow boiling
2002
·
M.Z. Hasan
, F. Najmabadi
, et al.
·
IEEE/NPSS Symposium on Fusion Engineering
·
1
Special Issue on Plenary and Invited Papers From Icops 2009
2010
·
S. P. Obenschain
, Ann Schmitt
, et al.
Engineering description of a solid first wall blanket based on advanced ferritic steel and re-circulating flibe
2006
·
I.N. Sviatoslavsky
, M.E. Sawan
, et al.
·
IEEE/NPSS Symposium on Fusion Engineering
Magnet design for the ARIES-II D-/sup 3/He reactor
2002
·
L. Bromberg
, J. Schultz
, et al.
·
IEEE/NPSS Symposium on Fusion Engineering
Interaction of Hydrogen Plasma with SiC/SiC Composite
1995
·
M. Okamoto
, T. Nakano
, et al.
·
Fusion Technology
Advanced composites for nuclear applications
1993
·
S. Sharafat
, F. Najmabadi
·
Transactions of the American Nuclear Society
Compendium of papers by the fusion reactor studies group
1991
·
C.G. Bathke
, L. Bromberg
, et al.
·
DSpace@MIT (Massachusetts Institute of Technology)
PDF
The safety designs for the TITAN reversed-field pinch reactor study
1989
·
C.P.C. Wong
, S.P. Grotz
, et al.
·
Fusion Engineering and Design
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Works count:
28
Citation count:
208
H-index:
7
I10-index:
6
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