A pulse-controlled modified-burst test instrument for accident-tolerant fuel cladding
Sign Up to like & getrecommendations! Published in 2017 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2017.05.058
Abstract: Abstract Pellet-cladding mechanical interaction due to thermal expansion of nuclear fuel pellets during a reactivity-initiated accident (RIA) is a potential mechanism for failure of nuclear fuel cladding. To investigate the mechanical behavior of cladding during… read more here.
Keywords: accident tolerant; fuel cladding; test;
Effect of aluminum oxide coated on fuel cladding surface on crud deposition in simulated PWR primary water
Sign Up to like & getrecommendations! Published in 2018 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2018.08.022
Abstract: Abstract Deposits on fuel assemblies (crud) have been the main cause of local power shift, increased fuel cladding temperature, accelerated fuel cladding corrosion, and radiation buildup in nuclear power plants. We report the experimental results… read more here.
Keywords: fuel; fuel cladding; cladding surface; crud deposition ... See more keywords
Compatibility studies on Mo–coating systems for nuclear fuel cladding applications
Sign Up to like & getrecommendations! Published in 2017 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2017.09.034
Abstract: Abstract To improve the safety factor of nuclear power plants in accident scenarios, molybdenum (Mo), with its high-temperature strength, is proposed as a potential fuel-cladding candidate. However, Mo undergoes rapid oxidation and sublimation at elevated… read more here.
Keywords: compatibility studies; studies coating; coating systems; fuel ... See more keywords
Studies on fuel-cladding chemical interaction between U−10 wt%Zr alloy and T91 steel
Sign Up to like & getrecommendations! Published in 2019 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2018.10.041
Abstract: Abstract The chemical interaction of U−Zr based fast reactor fuel with T91 grade steel cladding was investigated by employing DTA (differential thermal analysis), diffusion couple experiment and SEM/EDS, SEM/EBSD analyses. The DTA results revealed a… read more here.
Keywords: steel; t91 steel; chemical interaction; fuel cladding ... See more keywords
On the origins and the evolution of the fuel-cladding bonding phenomenon in PWR fuel rods
Sign Up to like & getrecommendations! Published in 2019 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2019.04.015
Abstract: Abstract This study proposes a new and detailed description of the fuel-cladding bonding phenomenon occurring in PWR fuel rods. Very early and late bonding states were characterized on specimens of 35.3 GWd.tU−1 moderate burnup and… read more here.
Keywords: bonding phenomenon; fuel; fuel cladding; pwr fuel ... See more keywords
U-10Zr and U-5Fs: Fuel/cladding chemical interaction behavior differences
Sign Up to like & getrecommendations! Published in 2020 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2019.151840
Abstract: Abstract A fuel performance phenomenon that has previously limited the peak cladding temperature of metallic fast reactor fuel is fuel/cladding chemical interaction (FCCI). This study examined the differences in the phenomenon exhibited by the more… read more here.
Keywords: cladding chemical; fuel; chemical interaction; fuel cladding ... See more keywords
Development of accident tolerant FeCrAl-ODS fuel cladding for BWRs in Japan
Sign Up to like & getrecommendations! Published in 2021 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2021.153276
Abstract: Abstract The FeCrAl-oxide dispersion strengthened (ODS) alloy is a promising candidate alloy for the accident tolerant fuel (ATF) cladding of light water reactors (LWRs) and has been recently developed in Japan. This paper reports on… read more here.
Keywords: fecral ods; fuel; fuel cladding; accident tolerant ... See more keywords
Development of anodization technique on zirconium silicide material for reproducing micro/nanosurface structure: Application to nuclear accident tolerant fuel cladding
Sign Up to like & getrecommendations! Published in 2019 at "Surface and Coatings Technology"
DOI: 10.1016/j.surfcoat.2019.05.086
Abstract: Abstract Zirconium silicide (ZrSi2) surfaces with micro/nanoscale structures were fabricated using an anodization technique with different working solutions. The surface structures evolved depending on the reaction time, and the resulting surface structures were characterized using… read more here.
Keywords: fuel cladding; anodization technique; zirconium silicide; zrsi2 ... See more keywords
Oxidation behavior of high-burnup advanced fuel cladding tubes in high-temperature steam
Sign Up to like & getrecommendations! Published in 2019 at "Journal of Nuclear Science and Technology"
DOI: 10.1080/00223131.2019.1613268
Abstract: ABSTRACT To evaluate the oxidation behavior of high-burnup advanced fuel cladding tubes in high-temperature steam, laboratory-scale isothermal oxidation tests were conducted using the following advanced fuel cladding tubes with burnups of up to 85 GWd/t:… read more here.
Keywords: oxidation; advanced fuel; cladding tubes; fuel cladding ... See more keywords
GTAW Welded Inconel 625 Alloy Fuel Cladding for the Canadian SCWR: Microstructure and Mechanical Property Characterization
Sign Up to like & getrecommendations! Published in 2020 at "Journal of Nuclear Engineering and Radiation Science"
DOI: 10.1115/1.4049278
Abstract: Inconel 625 is considered one of the candidate materials for reactor fuel cladding in the Canadian supercritical water reactor (SCWR) design. Gas tungsten arc welding (GTAW) is being evaluated as a joining technique for SCWR… read more here.
Keywords: gtaw; fuel cladding; microscopy; inconel 625 ... See more keywords
Investigation on Neutronic Parameters of the KLT-40S Reactor Core with U3Si2-FeCrAl using SCALE Code
Sign Up to like & getrecommendations! Published in 2023 at "Journal of Engineering and Technological Sciences"
DOI: 10.5614/j.eng.technol.sci.2023.55.1.3
Abstract: From a safety point of view, the fuel-cladding of the current design of the KLT-40S reactor still carries a potential risk in the event of a loss-of-coolant accident (LOCA) allowing the formation of hydrogen gas.… read more here.
Keywords: reactor; 40s reactor; u3si2 fecral; fuel cladding ... See more keywords