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of 6
pro vyhledávání: '"Barret Elward"'
Autor:
Rajnikant V. Umretiya, Atharva Chikhalikar, Barret Elward, Tiago A. Moreira, Mark Anderson, Raul B. Rebak, Jessika V. Rojas
Publikováno v:
Nuclear Materials and Energy, Vol 38, Iss , Pp 101567- (2024)
The APMT FeCrAl alloy is a cladding candidate for the accident-tolerant fuel (ATF) systems in light water reactors (LWRs) due to its ability to form a protective Al2O3 film on the surface at temperatures greater than 1000 °C. In order to understand
Externí odkaz:
https://doaj.org/article/06df0d6c6da949f39ee1f369fecafde1
Autor:
Barret Elward, Raul B. Rebak, Mark Anderson, Jessika V. Rojas, Rajnikant V. Umretiya, Donghwi Lee
Publikováno v:
Journal of Nuclear Materials. 557:153269
FeCrAl alloys are candidate materials for manufacturing accident-tolerant fuel (ATF) cladding intended for light water reactors to increase fuel reliability and safety during design-basis and beyond-design-basis accident scenarios. The evolution of t
Autor:
Barret Elward, Jessika V. Rojas, Raul B. Rebak, R. Uhorchuk, Rajnikant V. Umretiya, Mark Anderson, S. y Leon
Publikováno v:
Transactions of the American Nuclear Society - Volume 121.
Autor:
Mark Anderson, Rajnikant V. Umretiya, Raul B. Rebak, Jessika V. Rojas, Barret Elward, S. y Leon, R. Uhorchuk
Publikováno v:
Transactions of the American Nuclear Society - Volume 121.
Autor:
Matteo Bucci, Donghwi Lee, Barret Elward, Paul Brooks, Rajnikant V. Umretiya, Mark Anderson, Jessika V. Rojas, Raul B. Rebak
Publikováno v:
Applied Thermal Engineering. 185:116347
Flow boiling heat transfer tests were conducted to evaluate the Critical Heat Flux (CHF) and Heat Transfer Coefficient (HTC) of conventional and accident tolerant fuel (ATF) cladding materials, i.e., bare Zircaloy-4 (Zr4), and Zircaloy-4 coated with
Autor:
Jessika V. Rojas, Mark Anderson, Rajnikant V. Umretiya, Raul B. Rebak, Barret Elward, Donghwi Lee
Publikováno v:
Journal of Nuclear Materials. 541:152420
Accident-tolerant fuel (ATF) cladding materials aim to improve fuel reliability and safety during accident scenarios in water-cooled reactors. These ATF cladding should also perform comparable or better than the current zirconium alloy cladding under