Results 31 to 40 of about 5,051,565 (352)
Preparation process and performance of graphene oxide-doped UO2 pellets
BackgroundUranium dioxide (UO2) has been broadly employed as nuclear fuel in nuclear reactors. However, the poor thermal conductivity of UO2 compromises the safety of the reactor owing to possible sharp temperature gradients.
WEN Feng +6 more
doaj +1 more source
Evaluation of operational reliability of diesel fuel system elements [PDF]
In the article, as a result of a review and analysis of studies on the reliability of elements of the power system of diesel engines, it was determined that the cause of most failures of elements of the power system is the presence of impurities and ...
Yakubov Khushnud +4 more
doaj +1 more source
The Electric Current Effect on Electrochemical Deconsolidation of Spherical Fuel Elements
For High-Temperature Gas-Cooled Reactor in China, fuel particles are bonded into spherical fuel elements by a carbonaceous matrix. For the study of fuel failure mechanism from individual fuel particles, an electrochemical deconsolidation apparatus was ...
Xiaotong Chen +5 more
semanticscholar +1 more source
CERMET dispersion fuel is currently a hotspot in the research and development of fuels for nuclear thermal propulsion (NTP) reactors. Uranium nitride (UN) has a uranium density 40% greater than that of uranium dioxide (UO2), as well as the advantages of ...
LIU Wentao1, 2, DU Jiangping1, 2, ZHAO Yumeng1, 2, MA Chunyu2, LIU Wei1, 2, CAI Zhenfang2
doaj +1 more source
The high temperature gas-cooled reactors (HTGRs) are the next-generation reactors with high safety, because the cores of HTGRs would not melt. But it is important to improve the oxidation resistance of the fuel in case of a huge oxygen ingress into the ...
Jun AIHARA +2 more
doaj +1 more source
Outcomes of the “steady-state crisis” experiment in the MIR reactor channel [PDF]
To license nuclear fuel for nuclear power plants, data on the behavior of fuel elements (FE) under design-basis accidents are required. These data are obtained during tests of fuel assemblies (FA) and single fuel elements in research reactor channels ...
Aleksandr V. Alekseev +4 more
doaj +3 more sources
Metal Fuel Development and Verification for Prototype Generation IV Sodium-Cooled Fast Reactor
Metal fuel is being developed for the prototype generation-IV sodium-cooled fast reactor (PGSFR) to be built by 2028. U–Zr fuel is a driver for the initial core of the PGSFR, and U–transuranics (TRU)–Zr fuel will gradually replace U–Zr fuel through its ...
Chan Bock Lee +4 more
doaj +1 more source
The neutron radiography reactor (NRAD) is a 250 kW Mark-II Training, Research, Isotopes, General Atomics (TRIGA) reactor at Idaho National Laboratory, Idaho Falls, ID, USA.
A. Craft, B. Hilton, Glen C. Papaioannou
semanticscholar +1 more source
Microbial fuel cell (MFC) technology offers an alternative means for producing energy from waste products. In this review, several characteristics of MFC technology that make it revolutionary will be highlighted.
Sami G. A. Flimban +3 more
semanticscholar +1 more source
Corrosion tests in water of fuel elements irradiated in the world’s first NPP reactor [PDF]
Spent nuclear fuel (SNF) storage in reactor spent fuel pools (SFP) is one of the crucial stages of SNF management technology: it requires special measures to ensure nuclear and radiation safety.
Sergey N. Ivanov +4 more
doaj +3 more sources

