scholarly journals COBRA-II: A DIGITAL COMPUTER PROGRAM FOR THERMAL-HYDRAULIC SUBCHANNEL ANALYSIS OF ROD BUNDLE NUCLEAR FUEL ELEMENTS.

1970 ◽  
Author(s):  
D S Rowe
Keyword(s):  
Computer Program ◽  
Nuclear Fuel ◽  
Digital Computer ◽  
Rod Bundle ◽  
Fuel Elements ◽  
Subchannel Analysis

Large-Scale Pulsation Detection by Means of Temperature Measurements

2008 ◽  
Vol 130 (11) ◽  
Author(s):  
N. Silin ◽  
V. Masson ◽  
A. Rauschert
Keyword(s):  
Nuclear Fuel ◽  
Large Scale ◽  
Axial Flow ◽  
Temperature Measurements ◽  
Time Resolved ◽  
Structure Information ◽  
Rod Bundle ◽  
Nuclear Fuel Assembly ◽  
Large Scale Flow ◽  
Fuel Elements

In the present work we explore the potential of time-resolved temperature measurements to obtain information on large-scale pulsations in a rod bundle geometry with axial flow. Large-scale flow pulsation is the phenomenon that dominates the turbulent mixing between the subchannels of rod bundles, which explains why it is of great importance for the design or assessment of nuclear fuel elements. The objective of the present work is to determine the characteristics of large-scale pulsations that can be used for the verification or validation of computational fluid dynamics code results. The method proposed is to generate a temperature gradient across the location of flow pulsations and to measure the time-varying temperature field downstream. Pulsation characteristic times, lengths, and traveling speed have been obtained. This study has been performed in a rod bundle similar to a nuclear fuel assembly and the results obtained are in good agreement with previous works on similar geometries. The technique can be applied to obtain additional large-scale structure information in test sections designed for thermal measurements, in situations where convection is dominated by these structures.

Sub-channels thermal-hydraulic analysis of rod bundle nuclear fuel elements under rolling motions

2021 ◽  
pp. 108874
Author(s):  
M. Behzadi ◽  
A. Zolfaghari ◽  
M.R. Abbassi ◽  
A. Norouzi ◽  
M.M. Mirzaeegoudarzi
Keyword(s):  
Nuclear Fuel ◽  
Hydraulic Analysis ◽  
Rod Bundle ◽  
Fuel Elements ◽  
Thermal Hydraulic Analysis
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