Results 121 to 130 of about 142,006 (191)
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Volume 1: Low/Intermediate-Level Radioactive Waste Management; Spent Fuel, Fissile Material, Transuranic and High-Level Radioactive Waste Management, 2013
NUKEM monitor FAMOS is designed to measure the burn up of fuel assemblies (FA’s) and allows the calculation of the content of fissile material and other actinides. The knowledge of the isotopic composition and activities of FA’s is required for a safe handling and storage of the elements.
M. Sokcic-Kostic +3 more
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NUKEM monitor FAMOS is designed to measure the burn up of fuel assemblies (FA’s) and allows the calculation of the content of fissile material and other actinides. The knowledge of the isotopic composition and activities of FA’s is required for a safe handling and storage of the elements.
M. Sokcic-Kostic +3 more
openaire +1 more source
Finite element analysis of the mechanical behavior of a nuclear fuel assembly spacer grid
Nuclear Engineering and Design, 2019The purpose of this study is to develop a finite element model that accurately describes the mechanical behavior of a spacer grid. The spacer grid is the most important component of a nuclear fuel assembly and supports the fuel rod with a structurally ...
Y. Yoo, Kyoung-Hong Kim, K. Eom, S. Lee
semanticscholar +1 more source
International Journal of Heat and Fluid Flow, 2019
Invariant analysis of the Reynolds stress tensor anisotropy can give an accurate and deep intuitive understanding of the turbulent structure of a turbulent flow.
G. Busco, E. Merzari, Y. Hassan
semanticscholar +1 more source
Invariant analysis of the Reynolds stress tensor anisotropy can give an accurate and deep intuitive understanding of the turbulent structure of a turbulent flow.
G. Busco, E. Merzari, Y. Hassan
semanticscholar +1 more source
, 2020
A mechanical apparatus was developed to investigate the grid-to-rod fretting on nuclear assembly of Zr–1Nb–1Sn-0.1Fe alloy. Test apparatus allowed the performing of fretting tests on fuel rods at a frequency to 30 Hz, which was evaluated as the first ...
D. A. Baêta +3 more
semanticscholar +1 more source
A mechanical apparatus was developed to investigate the grid-to-rod fretting on nuclear assembly of Zr–1Nb–1Sn-0.1Fe alloy. Test apparatus allowed the performing of fretting tests on fuel rods at a frequency to 30 Hz, which was evaluated as the first ...
D. A. Baêta +3 more
semanticscholar +1 more source
A new method to simulate dispersion plate-type fuel assembly in a multi-physics coupled way
Annals of Nuclear Energy, 2022The plate-type fuel has an excellent thermal–mechanical behavior as a type of nuclear fuel. To simulate and analyze the behavior of plate-type fuel assembly under irradiation conditions, a fuel performance analysis code BEEs-Plates was developed based on
Fengrui Xiang +8 more
semanticscholar +1 more source
International Journal of Heat and Fluid Flow, 2018
The partially averaged Navier–Stokes turbulence model, which is a bridging model between the Reynolds averaged Navier–Stokes model and direct numerical simulation, is capable of directly resolving the turbulent scales of interest by filtering the Navier ...
G. Busco, Y. Hassan
semanticscholar +1 more source
The partially averaged Navier–Stokes turbulence model, which is a bridging model between the Reynolds averaged Navier–Stokes model and direct numerical simulation, is capable of directly resolving the turbulent scales of interest by filtering the Navier ...
G. Busco, Y. Hassan
semanticscholar +1 more source
Development of nuclear fuel assembly finite element model for mechanical integrity evaluation
Nuclear Engineering and Design, 2023Y. Yoo +3 more
semanticscholar +1 more source
Nuclear Technology
The helical cruciform fuel rod is a new fuel design. Its advantages include a large surface area–to-volume ratio, short thermal conductivity distance, and no need for grid spacers.
Weishu Wang, Pengzhi Wang, Xiaojie Zheng
semanticscholar +1 more source
The helical cruciform fuel rod is a new fuel design. Its advantages include a large surface area–to-volume ratio, short thermal conductivity distance, and no need for grid spacers.
Weishu Wang, Pengzhi Wang, Xiaojie Zheng
semanticscholar +1 more source
Vibrations of nuclear fuel assemblies: A simplified model
Nuclear Engineering and Design, 1985Abstract This paper is concerned with the resonance frequencies of nuclear reactor cores. The homogenized equations are obtained by representing the coupled cooling fluid-rod system as an equivalent continuous material. The homogenized dynamical equations are also derived and numerical procedures are presented in brief.
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Annals of Nuclear Energy, 2016
Abstract We investigated the thermal–hydraulic safety of spent fuel bundles installed in a mast assembly, assuming a lock-up accident of a fuel transfer system. For this, flow analysis with Computational Fluid Dynamics (CFD) for the natural convection and subsequent safety evaluation with 1-D Nuclear Power Plant (NPP) safety analysis code were ...
YoungSoo Kim +5 more
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Abstract We investigated the thermal–hydraulic safety of spent fuel bundles installed in a mast assembly, assuming a lock-up accident of a fuel transfer system. For this, flow analysis with Computational Fluid Dynamics (CFD) for the natural convection and subsequent safety evaluation with 1-D Nuclear Power Plant (NPP) safety analysis code were ...
YoungSoo Kim +5 more
openaire +1 more source