Thermal–hydraulic analysis of wire-wrapped SFR test subassemblies by subchannel analysis method

Pramuditya, Syeilendra; Takahashi, Minoru

doi:10.1016/j.anucene.2012.11.011

Cited by 19 publications

(4 citation statements)

References 14 publications

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“…The notation P a (1H) denotes the pressure drop in a pitch, that is, the values in Figure 5C. As shown in Figure 3 and Figure 4, the rotation direction of the wire‐wrap spacers is clockwise, and the decreasing order of the height of the wire‐wrap spacers in the edge subchannel 26,27 between the cross sections 3R and 4R are 2# (3#), 4#, 1#, and 5# (6#), leading to the relationship depicted in Figure 5D. The negative values indicate the pressure profile in the axial direction is nonlinear, the pressure drop in 1.5 pitches (between the pressure tap 35 and 45, and the pressure tap 36 and 46) is smaller than the average pressure drop in a pitch in the edge subchannels.…”

Section: Resultsmentioning

confidence: 96%

Periodicity and transversal pressure distribution in a Wire‐wrapped 19‐Pin fuel assembly

et al. 2020

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Summary An experimental setup was designed and constructed to investigate the detailed pressure distribution data of a wire‐wrapped fuel assembly and to evaluate the friction factor correlations. The test section was a wire‐wrapped 19‐pin fuel assembly manufactured with polymethyl methacrylate, and the working liquid was deionized water. A secondary circuit supplying chilled water was built to minimize the changes in the physical properties of the working liquid induced by temperature fluctuation. Eighteen axial differential pressure drops and twelve transversal differential pressure drops with Reynolds number in the range of 3750 to 16 250 were measured. The relation between the friction factor and Reynolds number was analyzed. The results showed that the axial pressure in the edge subchannels varied periodically similar to a helical pitch. The direction of rotation and height of the wire‐wrap spacers in the subchannels have a significant effect on the transversal pressure distribution, especially in the zones where the wire‐wrap spacers cross. Besides, the Rehme correlation and Cheng and Todreas Detailed (CTD) correlation showed the best fit with the experimental data. The critical Reynolds number, where the shift from the transitional to turbulent flow regions occurs, is approximately 11 700, and the difference between the experimental data and the value predicted by the CTD correlation was approximately 8.33%. The experimental data of the pressure distribution in the wire‐wrapped fuel assembly could complement the existing database, which supports the development of fast reactors.

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Section: Resultsmentioning

confidence: 96%

Periodicity and transversal pressure distribution in a Wire‐wrapped 19‐Pin fuel assembly

et al. 2020

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“…Finally heat conduction within the fluid is taken into consideration and included in the energy conservation equation. To confirm the prediction capability of the SFR version of the code, calculations and comparisons with available experimental data of 19-, 37-pin and 127pin sub-assemblies can be performed [49]. The validation of the code can also make use with Oak Ridge National Laboratory (ORNL) 19 pin tests [50].…”

Section: Hexagonal Latticementioning

confidence: 99%

Development of a Single-Phase, Transient, Subchannel Code, within the MOOSE Multi-Physics Computational Framework

2022

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Subchannel codes have been widely used for thermal-hydraulics analyses in nuclear reactors. This paper details the development of a novel subchannel code within the Idaho National Laboratory’s (INL) Multi-physics Object Oriented Simulation Environment (MOOSE). MOOSE is a parallel computational framework targeted at the solution of systems of coupled, nonlinear partial differential equations, that often arise in the simulation of nuclear processes. As such, it includes codes/modules able to solve the multiple linear and nonlinear physics that describe a nuclear reactor, under normal operation conditions or accidents. This includes thermal-hydraulics, fuel performance, and neutronics codes, between others. A MOOSE-based subchannel code is a new addition to the fleet of INL-developed codes, based on the MOOSE framework. In this work, we present the derivation of the subchannel equations for a single-phase fluid, we proceed with the description of the algorithm that is used to solve these equations and describe how this algorithm was implemented within MOOSE. We also present how this code can be coupled to the BISON fuel performance code. Next, we verify the friction model and the turbulent mixing model. We calibrate the turbulent modeling parameters for momentum mixing and enthalpy mixing, CT,β. We validate the code using experimental results and last demonstrate the coupling capabilities using a simple example.

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“…The latter considers the variation of axial geometric parameters with wire rotation. For example, if a sub‐channel is divided into 12 axial parts, as shown in Figure 2 33 . In each segment, the wire is assumed to be parallel to the rod and vertically straight.…”

Section: Overview Of Previous Investigationsmentioning

confidence: 99%

Improvement and validation of a sub‐channel analysis code for a lead‐cooled reactor with wire spacers

Wang

Gui

et al. 2020

Int J Energy Res

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Summary The fuel rods in the lead‐based fast reactor (LFR) are usually supported by wire spacer, and the presence of the wire results in the complexity of the thermal‐hydraulic analysis in rod bundles. In this study, several previous experimental research about lead‐bismuth eutectic flowing through the rod bundle are investigated. Based on the collected experimental data, a series of flow and heat transfer correlations in the wire‐fixed rod bundle are compared and evaluated. The recommended correlations are then implemented into the in‐house sub‐channel analysis code SACOS‐PB. Furthermore, to account for the changes in the channel cross‐section parameters caused by the wire spacer, two optional wire geometric treatments were added to the code: axially‐averaged approach and axially‐varied approach with extra cross‐flow enhancement model. 19‐rod bundle and 61‐rod bundle tests are used to validate the optimized code. The deviations for the temperature differences of cladding and coolant in internal sub‐channels are within 25%, and the axially‐varied approach shows a higher prediction accuracy, which proves that the improvement of the SACOS‐PB are reliable. This work could provide a reference for the subsequent design and development of the LFR core.

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Thermal–hydraulic analysis of wire-wrapped SFR test subassemblies by subchannel analysis method

Cited by 19 publications

References 14 publications

Periodicity and transversal pressure distribution in a Wire‐wrapped 19‐Pin fuel assembly

Periodicity and transversal pressure distribution in a Wire‐wrapped 19‐Pin fuel assembly

Development of a Single-Phase, Transient, Subchannel Code, within the MOOSE Multi-Physics Computational Framework

Improvement and validation of a sub‐channel analysis code for a lead‐cooled reactor with wire spacers

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