Raul Rebak

Dr. Raul Rebak


Research Focus & Metrics

Academic Career Length

28Years (1999-Present)

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

Representative Publications

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1 January 2019 in Journal of Nuclear Materials
Verified
Journal Article
Closed access
MSMiao Song
Miao Song
MWMi Wang
Mi Wang
XLXiaoyuan Lou
Xiaoyuan Lou
RRRaul Rebak
Raul Rebak
GWGary Was
Gary Was

28 March 2009 in Metallurgical and Materials Transactions A
Verified
Journal Article
Closed access
PDF file
JFJoseph Farmer
Joseph Farmer
JCJor-Shan Choi
Jor-Shan Choi
CSCheng Saw
Cheng Saw
JHJeffrey Haslam
Jeffrey Haslam
DDDan Day
Dan Day
LALou Aprigliano
Lou Aprigliano

1 August 2007 in Journal of Materials Research
Verified
Journal Article
Closed access
PDF file
JFJ.C. Farmer
J.C. Farmer
JHJ.J. Haslam
J.J. Haslam
SDS.D. Day
S.D. Day
TLT. Lian
T. Lian
CSC.K. Saw
C.K. Saw
LAL.F. Aprigliano
L.F. Aprigliano

1 August 2012 in Electrochimica Acta
Verified
Journal Article
Closed access
NZN.S. Zadorozne
N.S. Zadorozne
CGC.M. Giordano
C.M. Giordano
MRM.A. Rodríguez
M.A. Rodríguez
RCR.M. Carranza
R.M. Carranza
RRRaul Rebak
Raul Rebak

1 January 2005 in JOM
Verified
Journal Article
Closed access
PDF file
KEKenneth J. Evans
Kenneth J. Evans
AYAhmet Yilmaz
Ahmet Yilmaz
SDS. Daniel Day
S. Daniel Day
LWLana L. Wong
Lana L. Wong
JEJohn C. Estill
John C. Estill
RRRaul Rebak
Raul Rebak

12 December 2017 in EPJ Nuclear Sciences & Technologies
Verified
Journal Article
Open access
PDF file
RRRaul Rebak
Raul Rebak
After a tsunami caused plant black out at Fukushima, followed by hydrogen explosions, the US Department of Energy partnered with fuel vendors to study safer alternatives to the current UO2-zirconium alloy system. This accident tolerant fuel alternative should better tolerate loss of cooling in the core for a considerably longer time while maintaining or improving the fuel performance during normal operation conditions. General electric, Oak ridge national laboratory, and their partners are proposing to replace zirconium alloy cladding in current commercial light water power reactors with an iron-chromium-aluminum (FeCrAl) cladding such as APMT or C26M. Extensive testing and evaluation is being conducted to determine the suitability of FeCrAl under normal operation conditions and under severe accident conditions. Results show that FeCrAl has excellent corrosion resistance under normal operation conditions and FeCrAl is several orders of magnitude more resistant than zirconium alloys to degradation by superheated steam under accident conditions, generating less heat of oxidation and lower amount of combustible hydrogen gas. Higher neutron absorption and tritium release effects can be minimized by design changes. The implementation of FeCrAl cladding is a near term solution to enhance the safety of the current fleet of commercial light water power reactors.