Research of two‐phase density wave instability in reactor core channels with rolling motion

Tian, Wenxi; Lian, Qiang; Qiu, Suizheng; Su, G.H.

doi:10.1002/er.5444

Cited by 5 publications

(5 citation statements)

References 27 publications

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“…However, such a process is very difficult because there is almost no experimental result of flow instability in long channels for a water-cooled blanket. Therefore, a compromise is made that the analysis method in this study is validated by the comparison to experimental data obtained from vertical channels (Tian et al, 2020). The validation of the analysis method to predict flow instability under different pressures is shown in Figures 3, 4 using the experimental data from vertical channels.…”

Section: Validationmentioning

confidence: 99%

“…The characteristic equation and similarity parameters are derived by Ishii (Tian et al, 2020) to select the nondimensional numbers that could represent the typical stability in a thermalhydraulic system. N pch and N sub are finally chosen as the two dimensionless numbers, which are widely used by other researchers.…”

Section: Validationmentioning

confidence: 99%

“…The inclination of entrance and exit sections can influence the distribution of pressure drop in the single-phase zone and two-phase mixture. If the entrance and exit sections are all horizontal, the flow instability is dominated by the frictional pressure drop, which is usually out-phase with the inlet flow rate (Tian et al, 2020). On the other hand, if the entrance and exit sections are inclined, the gravitational pressure drop plays a more important role than that with the horizontal entrance and exit sections.…”

Section: Influence Of Inclinationmentioning

confidence: 99%

“…Unlike the open channel in the reactor core of a PWR, there is no flow mixing in the parallel channel of a fusion blanket because the flow channel is independent of each other. Therefore, flow instability occurs more easily between these channels (Tian et al, 2020). Due to the existence of manifold isolating channels from the external system, the flow rate may oscillate between parallel channels even if the pressure drop in the adjacent manifolds does not change.…”

Section: Introductionmentioning

confidence: 99%

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Parametric study of density wave instability in parallel channels of a water-cooled blanket in a fusion reactor

Lian,

Liang,

Liao

et al. 2023

Front. Energy Res.

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In fusion reactors, many blanket concepts are designed with water as a coolant to transfer high-density heat from the fusion reaction out of the reactor core. The coolant temperature and pressure are maintained as the validated use in water-cooled fission reactors. However, the flow channel in a water-cooled blanket is independent of each other, and there is no flow mixing between coolant channels. Therefore, flow instability may occur in the independent parallel channels in a water-cooled blanket due to its unique structure and heat distribution, especially under the high heat flux caused by plasma rupture. In this study, the parametric analysis of density wave instability is performed using a thermal-hydraulic code developed for independent parallel channels based on the homogeneous model for the two-phase flow. The parallel-channel system in a water-cooled ceramic breeder (WCCB) blanket of the China Fusion Engineering Experimental Reactor (CFETR) is established for its first wall structure. A small disturbance is introduced into the system to determine if it is stable under different conditions. It is found that the channel number has no obvious influence on the prediction of the flow instability boundary. Therefore, the two-channel system is adopted to investigate the influence of different parameters, such as the pressure, resistance, flow rate, and inclination, on the flow instability boundary of the parallel-channel system in the CFETR WCCB blanket. The results show that flow instability occurs more easily in this study compared to the traditional instability analysis, especially under high-pressure conditions. In general, conditions of high pressure, large flow rate, and no inclination can stabilize the system, while the influence of resistance is quite different under different conditions of resistance and pressure. The research work indicates that more attention should be paid to the joint influence of different parameters for the water-cooled blanket during its design and operation.

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Section: Validationmentioning

confidence: 99%

Section: Validationmentioning

confidence: 99%

Section: Influence Of Inclinationmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Parametric study of density wave instability in parallel channels of a water-cooled blanket in a fusion reactor

Lian,

Liang,

Liao

et al. 2023

Front. Energy Res.

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“…They found a particular range of inlet subcooling, above or below which instabilities occurred. Tian et al 18 studied the density wave instability in reactor core channels with rolling motion. They found that the influences of the nonuniform heat fluxes were different under different profiles.…”

Section: Introductionmentioning

confidence: 99%

Numerical analysis on flow instability of parallel channels in steam generator for sodium‐cooled fast reactor

Song

Zhang

et al. 2020

Int J Energy Res

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Summary Steam generator is the heat transfer component of sodium‐cooled fast reactor (SFR). It is possible to happen flow instability in the tubes of sodium heated once‐through steam generator (OTSG). In order to investigate the flow instability of parallel channels in sodium heated OTSG, a numerical analysis code called COSFIAS has been developed in Fortran language based on time‐domain method. The experimental data of parallel channels flow instability with uniform heating power condition and sodium heated condition have been applied to validate the code. The relative errors between calculation results and experimental data of uniform heating power condition are within 10%. The relative errors between calculation results and experimental data of sodium heated conditions are within 7%. The comparison results indicate that the COSFIAS program is reasonable and accurate for practical engineering application. In addition, the effects of important parameters on flow instability of parallel channels have been analyzed. From the calculation results some conclusions could be drawn: the decrease of water pressure would cause the increase of heat transfer power and destabilize the parallel channels system; in high subcooling region, the increase of inlet subcooling would stabilize the system; in low subcooling region, with the decrease of inlet subcooling, the parallel channels system would turn to be unstable and then return to be stable again; the increase of water mass flow rate could stabilize the parallel channels system.; the sodium heated condition is more stable than uniform heat flux condition in the same heat transfer power; the increase of sodium inlet temperature could destabilize the parallel channels system; the increase of sodium mass flow rate could destabilize the parallel channels system. In addition, the code could be applied to support the design work of sodium heated OTSG.

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Analysis of the natural circulation system characteristics with fuel rods under motion conditions

Zhang¹,

Yang²,

Tian³

et al. 2022

Annals of Nuclear Energy

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Research of two‐phase density wave instability in reactor core channels with rolling motion

Cited by 5 publications

References 27 publications

Parametric study of density wave instability in parallel channels of a water-cooled blanket in a fusion reactor

Parametric study of density wave instability in parallel channels of a water-cooled blanket in a fusion reactor

Numerical analysis on flow instability of parallel channels in steam generator for sodium‐cooled fast reactor

Analysis of the natural circulation system characteristics with fuel rods under motion conditions

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