Results 31 to 40 of about 4,122 (158)

Effect of the swirl angle on calcium carbide gas combustion characteristics of lower burner under annular shaft kiln

open access: yesCase Studies in Thermal Engineering, 2023
In order to solve the problem of high CO concentration in the emitted flue gas after adopting the flue gas recirculation technology in the annular shaft kiln, in this paper, the combustion characteristics of calcium carbide gas in swirl burners under the
Le Ye   +6 more
doaj   +1 more source

Study on the influence of geometric size of annular fuel element on thermal performance

open access: yesHe jishu, 2023
BackgroundCompared with conventional rod-type nuclear fuel, annular fuel has higher power density and better heat transfer efficiency, which can significantly improve the safety and economy of the reactor.PurposeThis study aims to investigate the effect ...
XIANG Zhaocai   +2 more
doaj   +1 more source

Numerical Simulation of Heat Transfer Characteristic with Cell Type Spacer Grid for Annular Fuel Sub-channel

open access: yesYuanzineng kexue jishu, 2022
Annular fuel is a new type of fuel used in pressurized water reactor. The fuel pellets are annular shape and loaded between internal and external cladding.
HU Liqiang;SHI Baolei;TIAN Zihao;JI Songtao;YANG Lixin;YANG Shihao;HE Xiaojun
doaj  

Lead-Cooled Fast Reactor Annular UN Fuel Design and Development of Performance Analysis Program

open access: yesFrontiers in Energy Research, 2021
A kind of annular uranium nitride (UN) fuel suitable for lead-cooled fast reactor applications has been designed in this study. The design is directly targeting two main issues of UN fuel: severe swelling and thermal decomposition of UN fuel at high ...
He Yuan   +14 more
doaj   +1 more source

Numerical Simulation Research on Critical Heat Flux of Annular Fuel

open access: yesYuanzineng kexue jishu
Annular fuel features dual cooling channels, inner and outer, which can significantly reduce core temperature, enhancing reactor core safety and economic efficiency.
HU Liqiang1, JI Songtao1, , HAN Zhijie1, HE Xiaojun1, XIAO Yao2, ZHAO Minfu1
doaj   +1 more source

Advanced characterization-informed machine learning framework and quantitative insight to irradiated annular U-10Zr metallic fuels

open access: yesScientific Reports, 2023
U-10Zr Metal fuel is a promising nuclear fuel candidate for next-generation sodium-cooled fast spectrum reactors. Since the Experimental Breeder Reactor-II in the late 1960s, researchers accumulated a considerable amount of experience and knowledge on ...
Fei Xu   +5 more
doaj   +1 more source

Geometric configuration of fuel assembly for small lightweight lead-bismuth reactor

open access: yesHe jishu, 2023
BackgroundThe neutronics and thermal-hydraulic characteristics of lead-bismuth cooled reactors are significantly affected by the geometric configuration of fuel assembly and lattice parameters.
WANG Chang   +5 more
doaj   +1 more source

Neutronic and thermal-hydraulic performance analysis of a novel thorium-based fuel in dual-cooled annular assemblies for SMR applications [PDF]

open access: yesEPJ Web of Conferences
A coupled neutronic and thermal-hydraulic assessment is performed for a dual-cooled annular fuel concept applied to light-water SMR conditions. A mixed thorium-based oxide, (Th-233U-235U)O2, is evaluated against conventional UO2 and solid-pin benchmarks ...
Rifai Hanan   +7 more
doaj   +1 more source

Neutronic Design for Heat Pipe Reactor With Annular and Accident Tolerant Fuels

open access: yesFrontiers in Energy Research, 2021
Several core designs of heat pipe reactors with megawatt power were proposed for extreme environments, such as the deep space, the deep sea, and the earthquake locations.
Boshuai Cai   +7 more
doaj   +1 more source

Flow and heat transfer characteristics of FLiNaK salt in an annular channel heater

open access: yesHe jishu, 2022
BackgroundThe simulation device is one-third scale of the 10 MW solid-fuel thorium molten-salt reactor (TMSR) and has the rated heat power of 370 kW.
YANG Yang   +3 more
doaj   +1 more source

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