scholarly journals Advanced ODS FeCrAl alloys for accident-tolerant fuel cladding

2014 ◽  
Author(s):  
Sebastien N Dryepondt ◽  
Kinga A Unocic ◽  
David T Hoelzer ◽  
Bruce A Pint
Keyword(s):  
Fuel Cladding ◽  
Fecral Alloys

scholarly journals Development of ODS FeCrAl alloys for accident-tolerant fuel cladding

2015 ◽  
Author(s):  
Sebastien N. Dryepondt ◽  
David T. Hoelzer ◽  
Bruce A. Pint ◽  
Kinga A. Unocic
Keyword(s):  
Fuel Cladding ◽  
Fecral Alloys

scholarly journals Resistance of Ferritic FeCrAl Alloys to Stress Corrosion Cracking for Light Water Reactor Fuel Cladding Applications

CORROSION ◽  
10.5006/3632 ◽  
2020 ◽  
Vol 76 (11) ◽  
Author(s):  
Raul B. Rebak ◽  
Liang Yin ◽  
Peter L. Andresen
Keyword(s):  
High Temperature ◽  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Fuel Cycle ◽  
Austenitic Stainless Steels ◽  
Corrosion Cracking ◽  
Fuel Cladding ◽  
Light Water ◽  
Water Reactor ◽  
Fecral Alloys

Since 2011, the international nuclear materials community has been engaged in finding replacements for zirconium alloys fuel cladding for light water reactors. Iron-chromium-aluminum (FeCrAl) alloys are cladding candidates because they have high strength at high temperature and an extraordinary resistance to attack by superheated steam in the event of a loss of coolant accident. As FeCrAl alloys have never been used in nuclear reactors, it is important to characterize their behavior in the entire fuel cycle. Stress corrosion cracking (SCC) studies were conducted for two FeCrAl alloys (APMT and C26M) in typical simulated boiling water reactor conditions at 288°C containing either dissolved hydrogen or oxygen. Crack propagation studies showed that both ferritic FeCrAl alloys were resistant to SCC at stress intensities below 40 MPa√m. Current results for FeCrAl confirm previous findings for Fe-Cr alloys showing that ferritic stainless alloys are generally much more resistant to high-temperature water SCC than austenitic stainless steels.

Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding

2020 ◽  
Vol 536 ◽  
pp. 152221 ◽  
Author(s):  
Stephen S. Raiman ◽  
Kevin G. Field ◽  
Raul B. Rebak ◽  
Yukinori Yamamoto ◽  
Kurt A. Terrani
Keyword(s):  
Fuel Cladding ◽  
2Nd Generation ◽  
Fecral Alloys

Theory-guided bottom-up design of the FeCrAl alloys as accident tolerant fuel cladding materials

2019 ◽  
Vol 516 ◽  
pp. 63-72 ◽  
Author(s):  
Keke Chang ◽  
Fanping Meng ◽  
Fangfang Ge ◽  
Gongshu Zhao ◽  
Shiyu Du ◽  
...  
Keyword(s):  
Fuel Cladding ◽  
Bottom Up ◽  
Fecral Alloys

scholarly journals Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding

2018 ◽  
Vol 501 ◽  
pp. 59-71 ◽  
Author(s):  
Sebastien Dryepondt ◽  
Kinga A. Unocic ◽  
David T. Hoelzer ◽  
Caleb P. Massey ◽  
Bruce A. Pint
Keyword(s):  
Fuel Cladding ◽  
Fecral Alloys

Corrosion of FeCrAl alloys used as fuel cladding in nuclear reactors

2021 ◽  
Vol 869 ◽  
pp. 159235
Author(s):  
Guanyu Jiang ◽  
Donghai Xu ◽  
Peng Feng ◽  
Shuwei Guo ◽  
Jianqiao Yang ◽  
...  
Keyword(s):  
Nuclear Reactors ◽  
Fuel Cladding ◽  
Fecral Alloys

scholarly journals Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding

2019 ◽  
Vol 21 ◽  
pp. 100715 ◽  
Author(s):  
Tyler Dabney ◽  
Greg Johnson ◽  
Hwasung Yeom ◽  
Ben Maier ◽  
Jorie Walters ◽  
...  
Keyword(s):  
Cold Spray ◽  
Experimental Evaluation ◽  
Zirconium Alloy ◽  
Fuel Cladding ◽  
Fecral Alloys

scholarly journals Surface wettability and pool boiling Critical Heat Flux of Accident Tolerant Fuel cladding-FeCrAl alloys

2018 ◽  
Vol 338 ◽  
pp. 218-231 ◽  
Author(s):  
Amir F. Ali ◽  
Jacob P. Gorton ◽  
Nicholas R. Brown ◽  
Kurt A. Terrani ◽  
Colby B. Jensen ◽  
...  
Keyword(s):  
Heat Flux ◽  
Critical Heat Flux ◽  
Pool Boiling ◽  
Surface Wettability ◽  
Fuel Cladding ◽  
Fecral Alloys

scholarly journals Deformation Behavior in Neutron Irradiated Generation II FeCrAl Alloys for Accident Tolerant Fuel Cladding

2017 ◽  
Author(s):  
Kevin G. Field ◽  
Dalong Zhang ◽  
Maxim N. Gussev ◽  
Kurt R. Smith ◽  
Ken Littrell
Keyword(s):  
Deformation Behavior ◽  
Fuel Cladding ◽  
Fecral Alloys
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