Results 11 to 20 of about 3,448 (263)
Temperature fields and heat transfer in free-packed fuel pin bundles cooled by heavy liquid metal
Nuclear Energy and Technology, 2016 The paper considers heat transfer and temperature fields in a free-packed fuel pin bundle cooled by a heavy liquid metal with different types of spacing.
A.V. Zhukov +3 more
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Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor
Nuclear Engineering and Technology, 2019 Targeting at simulating the application of thorium-uranium (TU) fuel in the CANDU-6 reactor, this paper analyzes the process using the code DRAGON/DONJON where the discrete TU fuel pins are applied in the CANDU-6 reactor under the time-average ...
Nianbiao Deng +7 more
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Nuclear Engineering and Technology, 2019 In case of multiple failure scenario, such as LOCA with ECCS failure, the decay heat continues to raise the reactor core temperature, eventually leading to the core voiding.
Mukesh Sharma +3 more
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Sub-channel CFD for nuclear fuel bundles [PDF]
Nuclear Engineering and Design, 2019 This paper presents a novel Computational Fluid Dynamics (CFD)-based sub-channel framework for nuclear power plants, which combines the advantageous features of modern CFD and traditional 1-D sub-channel codes. The new method is capable of producing CFD-level 3-D results with locally desirable refinement when coupled with embedded resolved models, but ...
Liu, B., He, S., Moulinec, C., Uribe, J.
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Design and Fabrication of Remote Welding Equipment in a Hot-Cell
Science and Technology of Nuclear Installations, 2013 The remote welding equipment for nuclear fuel bundle fabrication in a hot-cell was designed and developed. To achieve this, a preliminary investigation of hands-on fuel fabrication outside a hot-cell was conducted with a consideration of the constraints ...
Soosung Kim +3 more
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Mechanical Engineering Journal, 2021 A sodium-cooled fast reactor has been designed to attain a high burn-up core in commercialized fast reactor cycle systems. The sodium-cooled fast reactor adopts a wire spacer between fuel pins.
Kosuke AIZAWA +4 more
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Vibration of fuel bundles [PDF]
, 1975 Several mathematical models have been proposed for calculating fuel rod responses in axial flows based on a single rod consideration. The spacing between fuel rods in liquid metal fast breeder reactors is small; hence fuel rods will interact with one another due to fluid coupling.
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Fretting Wear and Fatigue Life Analysis of Fuel Bundles Subjected to Turbulent Axial Flow in CEFR
Science and Technology of Nuclear Installations, 2019 In a fast spectrum reactor, the fuel rod bundle is mainly positioned radially by the wire which can make contact with the adjacent fuel rods, and then it is inevitable that flow-induced vibration (FIV) will cause fretting wear and vibration fatigue of ...
Yafeng Shu +3 more
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Numerical simulation of two-phase flow in 4x4 simulated bundle
Mechanical Engineering Journal, 2020 An evaluation methodology of a thermal-hydraulics based on a mechanism in light water reactors (LWRs) is needed from a viewpoint of the safety analysis during normal operation and unanticipated transient such as under a severe accident.
Ayako ONO +3 more
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Numerical investigation of the critical heat flux in a 5 × 5 rod bundle with multi-grid
Nuclear Engineering and Technology, 2022 To improve the heat transfer efficiency of the reactor fuel assembly, it is necessary to accurately calculate the two-phase flow boiling characteristics and the critical heat flux (CHF) in the fuel assembly.
Wei Liu +7 more
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