Experimental study on the natural circulation capability and heat transfer characteristic of liquid lead bismuth eutectic

Shi, Leitai; Su, G.H.; Zhu, Fengjie; Tan, Bing; Hou, Yandong; Wei, Shiying; Wang, Chenglong; Tian, Wenxi; Qiu, Suizheng; Wu, Junmei

doi:10.1016/j.pnucene.2019.03.003

Cited by 9 publications

(3 citation statements)

References 15 publications

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“…The Natural Circulation Capability Loop (NCCL) facility with its primary and secondary sides is schematically shown in Figure 7. The loop is rectangular in shape of 3.5 m height and 1 m width consisting of a heating section, cooling section, electromagnetic (EM) flowmeter, and EM flowmeter calibration tube (Shi, 2018;Shi et al, 2019). All parts in contact with LBE are made of 316L stainless steel.…”

Section: Description Of Nccl Facilitymentioning

confidence: 99%

“…Li et al (2015) have conducted several natural circulation tests at the KYLIN-II facility. Shi (2018) and Shi et al (2019) have designed a Natural Circulation Capability Loop (NCCL) to experimentally study the natural circulation startup process and capability of natural circulation under different conditions. In Korea, an integral test loop for operability and safety of PEACER has been setup (Jeong, 2006).…”

Section: Introductionmentioning

confidence: 99%

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Assessment of Modified RELAP5 MOD3.2 Against LBE Natural Circulation Test Loops

Liu

et al. 2021

Front. Energy Res.

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Motivated by the significant natural circulation capability of lead–bismuth eutectic (LBE)–cooled systems, the RELAP5 MOD3.2 code was modified for the analysis of LBE-cooled reactors and non-nuclear systems. The thermo-physical properties of LBE have been incorporated into the code without affecting the code’s original performance; new heat transfer correlations for liquid metal have been implemented. For the purpose of validating the modified code, experimental results of two different LBE natural circulation test loops were compared with the code simulation results. The first one was a natural circulation setup process test at a power of 22.5 kW performed at the Natural Circulation Experimental (NACIE) facility. The simulated inlet and outlet LBE temperatures across the heat source and mass flow rate of LBE agreed well with the test data. The second one was natural circulation conditions under five different power levels conducted at the Natural Circulation Capability Loop (NCCL) facility. The LBE temperature difference and mass flow rate under different power levels predicted by the code were consistent with the experimental data. Generally speaking, the modified code gives acceptable results, and the code could be applied for further LBE systems thermal-hydraulic analysis.

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Section: Description Of Nccl Facilitymentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Assessment of Modified RELAP5 MOD3.2 Against LBE Natural Circulation Test Loops

Liu

et al. 2021

Front. Energy Res.

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“…What's more, the oxygen control technology has been applied by CORRIDA loop in KIT, COLONRI I loop in Nuclear Research Institute Rež of Czech Republic, DELTA loop in Los Alamos National Laboratory, LECOR in ENEA, and SM‐2 as well as TT‐2M loop in Russia 25‐28 . Besides, for carrying out the experimental study on the natural circulation capability of LBE, TALL, NCCL, and KTL facilities were built by KTH Royal Institute of Technology, XJTU‐NuTheL, and Bhabha Atomic Research Centre, respectively 29‐31 …”

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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