A THERMAL-HYDRAULIC SUBCHANNEL ANALYSIS FOR ROD BUNDLE NUCLEAR FUEL ELEMENTS

1970 ◽  
Author(s):  
D. S. Rowe
Keyword(s):  
Nuclear Fuel ◽  
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

A Mathematical Model for Transient Subchannel Analysis of Rod-Bundle Nuclear Fuel Elements

1973 ◽  
Vol 95 (2) ◽  
pp. 211-217 ◽  
Author(s):  
D. S. Rowe
Keyword(s):  
Mathematical Model ◽  
Nuclear Fuel ◽  
Flow Rate ◽  
Transient Flow ◽  
Momentum Equation ◽  
Flow Area ◽  
Inlet Flow ◽  
Rod Bundle ◽  
Inlet Flow Rate ◽  
Fuel Elements

This paper presents a mathematical method for analyzing transient flow and enthalpy transport in rod-bundle nuclear fuel elements during both boiling and nonboiling conditions. A mathematical model is formulated by dividing the bundle flow area into flow subchannels that are assumed to contain one-dimensional flow and are coupled to each other by turbulent and diversion crossflow mixing. The mathematical model neglects sonic velocity propagation and neglects temporal and spatial acceleration in the transverse momentum equation. A semiexplicit finite-difference scheme is used to perform a boundary-value solution where the boundary conditions are the inlet enthalpy, inlet flow rate, and exit pressure. Calculations are presented to show the effect of rapid changes in heat flux, inlet enthalpy, and inlet flow rate on the subchannel flow and enthalpy distribution in rod bundles.

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