Experimental study on heat transfer of supercritical water flowing downward in circular tubes

Zhao, Meng; Gu, Haihua; Xu, Cheng

doi:10.1016/j.anucene.2013.07.003

Cited by 60 publications

(25 citation statements)

References 11 publications

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“…The SCW heat transfer experiment is carried out by Zhao et al (2013) in a vertical square-arrayed 2 Â 2 rod bundle. In their experiments Zhao et al (2013) measured the inner surface temperature of the heated rods when the SCW flows upward in the bundle.…”

Section: Experiments Conditionsmentioning

confidence: 99%

“…present paper the SCW heat transfer experiment in a 2 Â 2 rod bundle is calculated with the commercial CFD package, CFX 5.6. The calculation results with several turbulence models are validated with recent experiment (Zhao et al, 2013). The CFD calculation results based on the selected reliable turbulence are then utilized to evaluate the existing correlations to investigate their accuracy in predicting the SCW heat transfer in rod bundles.…”

Section: Introductionmentioning

confidence: 99%

“…Among the precious literature, Dyadyakin and Popov performed experiments in a 7-rod bundle with helical fins cooled with supercritical water and developed a local heat transfer correlation based on their experiment data (Dyadyakin and Popov, 1977). And recently Zhao et al (2013) carried out the SCW heat transfer experiment in a 2 Â 2 rod bundle. In contrast there are numerous literature dedicated on the numerical investigation of SCW heat transfer in SCs or rod bundles (Cheng et al, 2007a;Kiss et al, 2010;Shang and Lo, 2010;Yang et al, 2007;Zhu et al, 2014).…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Numerical analysis on supercritical water heat transfer in a 2 × 2 rod bundle

Xiong

Yang

2015

Annals of Nuclear Energy

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Section: Experiments Conditionsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Numerical analysis on supercritical water heat transfer in a 2 × 2 rod bundle

Xiong

Yang

2015

Annals of Nuclear Energy

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“…According to [32], Figure 7 is the cross section of test section 2 × 2 rod bundle arranged in square lattice. Four tubes made of Inconel-718 are heated by electricity, and the temperature of their inner surface is measured by sliding thermocouples.…”

Section: Rementioning

confidence: 99%

A circumferentially non-uniform fuel model and its application to thermal-hydraulic code

Yang

Liu

2017

Int J Energy Res

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SUMMARYIn the fuel assemblies in reactor core, the distribution of temperature is not uniform in the fuel rod along the circumferential direction. The circumferential temperature difference could be neglected for conventional assembly design but increases significantly in a tight lattice.To investigate the circumferential non-uniformity of heat transfer in rod bundles, this paper firstly establishes mathematical model and makes theoretical analyses, based on which influential non-dimensional numbers are summarized. Then, a semi-empirical correlation describing this phenomenon is proposed based on theoretical results and CFD sensitivity analyses. Finally, a three-dimensional model for cylindrical fuel is introduced in the thermal-hydraulic code to predict circumferential heat transfer non-uniformity in different geometry and flow conditions. To validate this model, some results are compared with experimental data of bundle test for subcritical and supercritical water.The three-dimensional fuel model for sub-channel code is a new numerical tool to predict the peak cladding and fuel temperature and can be applied in thermal-hydraulic analysis of fuel assemblies of tight lattice design.

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“…However, the validation work for the trans-critical models in these codes is still missing . The test facility Supercritical WAter MUltiPurpose loop (SWAMUP) in Shanghai Jiao Tong University (SJTU) has been built to perform this depressurization transient test (Zhao et al, 2014). Some pre-test calculations are important and necessary to show the feasibility of the experiment.…”

Section: Introductionmentioning

confidence: 99%

Thermal-Hydraulic Analysis of SWAMUP Facility Using ATHLET-SC Code

2015

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During the loss of coolant accident (LOCA) of supercritical water-cooled reactor (SCWR), the pressure in the reactor system will undergo a rapid decrease from the supercritical pressure to the subcritical condition. This process is called trans-critical transients, which is of crucial importance for the LOCA analysis of SCWR. In order to simulate the trans-critical transient, a number of system codes for SCWR have been developed up to date. However, the validation work for the trans-critical models in these codes is still missing.The test facility Supercritical WAter MUltiPurpose loop (SWAMUP) with 2 × 2 rod bundle in Shanghai Jiao Tong University (SJTU) will be applied to provide test data for code validation. Some pre-test calculations are important and necessary to show the feasibility of the experiment. In this study, trans-critical transient analysis is performed for the SWAMUP facility with the system code ATHLET-SC, which is modified in SJTU, for supercritical water system. This paper presents the system behavior, e.g., system pressure, coolant mass flow, cladding temperature during the depressurization. The effects of some important parameters such as heating power, depressurization rate on the system characteristics are also investigated in this paper. Additionally, some sensitivities study of the code models, e.g., heat transfer coefficient, critical heat flux correlation are analyzed and discussed. The results indicate that the revised system code ATHLET-SC is capable of simulating thermal-hydraulic behavior during the trans-critical transient. According to the results, the cladding temperature during the transient is kept at a low value. However, the pressure difference of the heat exchanger after depressurization could reach 6 MPa, which should be considered in the experiment.

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Experimental study on heat transfer of supercritical water flowing downward in circular tubes

Cited by 60 publications

References 11 publications

Numerical analysis on supercritical water heat transfer in a 2 × 2 rod bundle

Numerical analysis on supercritical water heat transfer in a 2 × 2 rod bundle

A circumferentially non-uniform fuel model and its application to thermal-hydraulic code

Thermal-Hydraulic Analysis of SWAMUP Facility Using ATHLET-SC Code

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