Study on Pb-Bi natural circulation phenomena

Takahashi, Minoru; Sofue, H.; Iguchi, Tatsuo; Matsumoto, Masaharu; Huang, Fei; Pramono, Yudi; Matsuzawa, Tomohiro; Uchida, Shouji

doi:10.1016/j.pnucene.2005.05.058

Cited by 25 publications

(7 citation statements)

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“…Flow regimes, heating conditions, channel geometries, and wall roughness play the dominant roles. In SUBAS, the friction coefficient is calculated by Cheng‐Todreas correlations, which are recommended by M. Takahashi in PBWFR research Properties of liquid lead‐bismuth alloy …”

Section: Descriptions Of Sub‐channel Analysis Code Subasmentioning

confidence: 99%

Sub-channel analysis for Pb-Bi-cooled direct contact boiling water fast reactor

et al. 2018

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Summary Pb‐Bi‐cooled direct contact boiling water fast reactor (PBWFR) featured with a direct‐contact heat exchanger between lead‐bismuth eutectic coolant and water could significantly simplify the primary system and enhance the natural circulation capability, meeting the potential needs for small modular reactor design. It is of great importance to conduct thermal‐hydraulic analysis of the PBWFR core in detail. In this paper, a self‐developed SUB‐channel AnalysiS code SUBAS is adopted to study the thermal hydraulic characteristics of the PBWFR core. The fidelity and the reliability of the code have been preliminarily benchmarked. With SUBAS, the space grid is studied to figure out its impact on the temperature and flow distributions in each sub‐channel. Besides, the application of space grids would increase the pressure drops and decreases the cross flow between adjacent sub‐channels. To study the transient performance of the PBWFR core, the power transient and the inlet blockage accident are calculated by SUBAS. The results of the power transient show the cross‐flow effect would be weakened in the sub‐channel which has higher coolant temperature and larger mass flow rate. For the inlet blockage accident, the results indicate the influence of the small area blockage is relatively weak on the overall performance of the assembly but is significant on the local parameters. With consideration of time and space, the blockage influence only exists in a certain area. This research may provide contribution to the design of PBWFR.

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Section: Descriptions Of Sub‐channel Analysis Code Subasmentioning

confidence: 99%

Sub-channel analysis for Pb-Bi-cooled direct contact boiling water fast reactor

et al. 2018

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“…The detail equation of pressure losses can be found in Ref. (9). Pb-Bi flow rate was estimated by equating the driving head of Pb-Bi circulation in Eq.…”

Section: System and Balance Conditionmentioning

confidence: 99%

“…Takahashi et al (9,10) studied two-phase flow behavior of steam-water and Pb-Bi experimentally using Pb-Bi-water direct contact boiling two-phase flow loop and reported experimental data of Pb-Bi flow rate induced by water injection into the Pb-Bi flow. The two-phase flow characteristics in the tube were evaluated analytically by assuming force balance between buoyancy force of two phase flow and total pressure drop in the Pb-Bi loop including two-phase flow pressure drop in the chimney (7,10) .…”

Section: Introductionmentioning

confidence: 99%

Experimental and Analytical Study of Lead-Bismuth-Water Direct Contact Boiling Two-Phase Flow

Novitrian

Dostál

Takahashi

2007

JPES

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The characteristics of lead-bismuth(Pb-Bi)-water boiling two-phase flow were investigated experimentally and analytically using a Pb-Bi-water direct contact boiling two-phase flow loop. Pb-Bi flow rates and void fraction were measured in a vertical circular tube at conditions of system pressure 7MPa, liquid metal temperature 460°C and injected water temperature 220°C. The drift-flux model with the assumption that bubble sizes were dependent on the fluid surface tension and the density ratio of Pb-Bi to steam-water mixture was chosen and modified by the best fit to the measured void fraction. Pb-Bi flow rates were analytically estimated using balance condition between buoyancy force and pressure losses, where the buoyancy force was calculated from void fraction estimated using the modified drift-flux model. The deviation of the analytical results of the flow rates from the experimental ones was less than 10%.

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“…Tarantino and Bernardi (2010) performed LBE NC tests with gas-injection on the NACIE loop and CIECE pool test facility to verify the code post-test in ENEA. Moreover, the stable LBE NC had been obtained from experiments by Takahashi (2005), Choa and Batta (2011) and Borgohain and Jaiswal (2011) performed at different conditions. Some experiments mentioned above were carried out for HLM NC study.…”

Section: Introductionmentioning

confidence: 99%