Results 11 to 20 of about 871,934 (285)

Flux Density Distribution Measurement in Annular Fuel Reactor

open access: yesYuanzineng kexue jishu, 2022
The relative neutron flux density distribution is one of the essential physical parameters of the reactor. Measuring the relative neutron flux density distribution of the annular fuel zero-power reactor core has guiding significance for understanding the
ZHANG Geng;LIU Feng;XIA Zhaodong;ZHU Qingfu;ZHANG Zhifeng
doaj   +1 more source

Large eddy simulation of fuel injection and spray combustion in an engine environment [PDF]

open access: yes, 2009
This thesis was submitted for the degree of Doctor of Philosophy and awarded by Brunel University.Large eddy simulation of spray combustion in an HSDI engine is carried out in this thesis.
Jaguś, Krzysztof
core   +8 more sources

Fertile-Free Annular Fuel for Plutonium Recycling

open access: yesNuclear Technology, 2007
Up to 50% increase in the power density of the existing pressurized water reactor (PWR)-type reactors can be achieved by the use of internally and externally cooled annular fuel geometry. As a result, the accumulated stock-piles of Pu, especially if incorporated infertile-free inert matrix, can be burnt at a substantially higher rate as compared with ...
Eugene Shwageraus   +2 more
openaire   +2 more sources

Investigation on radial fuel relocation and its influence on heat split phenomenon of dual-cooled annular fuel element

open access: yesInternational Journal of Advanced Nuclear Reactor Design and Technology, 2022
Radial fuel relocation due to fuel fragmentation can significantly change the heat split, further affecting the thermal performance and safety of dual-cooled annular fuels.
Yangbin Deng, Zijian Xu, Yuan Yin
doaj   +1 more source

Neutronic and Thermalhydraulic Evaluation of Annular Fuel in PWR with Three Different Nanofluids

open access: yesSakarya Üniversitesi Fen Bilimleri Enstitüsü Dergisi, 2022
In pressurized nuclear reactors, one of the fuel design principles is the fuel centerline temperature limit. Since the thermal conductivity of UO2 is not high, the temperature increases rapidly from the fuel surface to the fuel center.
Ali Tiftikçi
doaj   +1 more source

Thermal-hydraulic analysis method for the annular fuel structure of lead-bismuth reactor

open access: yesHe jishu, 2021
BackgroundAnnular fuel can significantly increase the power density of the lead-bismuth reactor core, which is of great significance to realize miniaturized design of the reactor and fuel economy improvement.PurposeThis study aims to develop an annular ...
WANG Ting   +4 more
doaj   +1 more source

Neutronics calculation of the conceptual TRISO duplex fuel rod design

open access: yesNuclear Materials and Energy, 2021
The duplex fuel pellet includes UO2 components as seed and ThO2 blanket, originally designed to increase the breeding rate of fissile materials in light water breeder reactors. However, the seed portion alone concentrates most of the energy released from
Mohamad Hairie Rabir   +2 more
doaj   +1 more source

The design of high power density annular fuel for LWRs [PDF]

open access: yes, 2004
Fuel performance models have been developed to assess the performance of internally and externally cooled LWR annular fuel. Such fuel may be operated at 30-50% higher core power density than the current operating LWRs, and to a burnup of 80-100MWd/kgU. The models are used to optimize the fuel design so that it is able to achieve high power density and ...
Yuan, Yi, 1975-
openaire   +2 more sources

Thermal-hydraulic characteristics in inner and outer wire-wrapped for a fast reactor annular fuel assembly

open access: yesFrontiers in Energy Research, 2022
The annular fuel has dual-cooled surfaces internally and externally. Compared with traditional cylindrical fuel, the inner flow field is introduced on the annular fuel assembly, and wire-wrapped can influence the inner flow field.
Yuefeng Guo   +10 more
doaj   +1 more source

RESONANCE CALCULATION BASED ON THE GLOBAL-LOCAL METHOD FOR THE COMPLEX GEOMETRY PROBLEMS [PDF]

open access: yesEPJ Web of Conferences, 2021
With the development of nuclear reactor, new complicated designs introduce some challenges for the resonance method in the NECP-X code, which is called as the Global-Local method. There are two limitations of the present NECP-X.
Cao Lu   +3 more
doaj   +1 more source

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