Cross-Scale Coupling Analysis Method for Otsg in Sfr and its Application

25 Pages Posted: 16 Jun 2023

See all articles by Zhenguo ZHANG

Zhenguo ZHANG

Harbin Engineering University

Xiaochang Li

Harbin Engineering University

Sichao Tan

Harbin Engineering University - Heilongjiang Provincial Key Laboratory of Nuclear Power System and Equipment

Ruifeng Tian

Harbin Engineering University - Heilongjiang Provincial Key Laboratory of Nuclear Power System and Equipment

Kai LIU

Harbin Engineering University

Hui CHENG

Harbin Engineering University

Abstract

This paper based on the full-regime flow boiling heat transfer model and the flow pattern discrimination model, a one-dimensional full-regime flow boiling heat transfer model from subcooled water to superheated steam on tube-side and its cross-scale coupling solution model with the three-dimensional refined CFD model on the shell side are established. The effectiveness of the coupling analysis model was verified by comparative analysis with experimental data. The independent coupling of the water-side of the OTSG with the sodium-side 3D fluid domain is realized. The results show that the cross-scale coupling method can accurately predict the temperature distribution and the main heat transfer characteristic points on the full height of tubes, and can obtain the temperature difference between each tubes and tube walls. The cross-scale coupled method avoids the direct adoption of the multiphase flow model, which significantly improves the efficiency and stability of the solution of the full-size OTSG.

Keywords: OTSG, Cross-scale coupling analysis, Boiling heat transfer, Three-dimensional temperature field, Seven-tube prototype model

Suggested Citation

ZHANG, Zhenguo and Li, Xiaochang and Tan, Sichao and Tian, Ruifeng and LIU, Kai and CHENG, Hui, Cross-Scale Coupling Analysis Method for Otsg in Sfr and its Application. Available at SSRN: https://ssrn.com/abstract=4481877 or http://dx.doi.org/10.2139/ssrn.4481877

Zhenguo ZHANG

Harbin Engineering University ( email )

Harbin, 150001
China

Xiaochang Li (Contact Author)

Harbin Engineering University ( email )

Harbin, 150001
China

Sichao Tan

Harbin Engineering University - Heilongjiang Provincial Key Laboratory of Nuclear Power System and Equipment ( email )

Ruifeng Tian

Harbin Engineering University - Heilongjiang Provincial Key Laboratory of Nuclear Power System and Equipment ( email )

Kai LIU

Harbin Engineering University ( email )

Harbin, 150001
China

Hui CHENG

Harbin Engineering University ( email )

Harbin, 150001
China

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