An experimental study on natural circulation decay heat removal system for a loop type fast reactor

Ono, Ayako; Kamide, Hideki; Kobayashi, Jun; Doda, Norihiro; Watanabe, Osamu

doi:10.1080/00223131.2015.1121844

Cited by 14 publications

(3 citation statements)

References 3 publications

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“…To perform heat transfer experiments using liquid sodium at up to 500 °C, and even 600 °C temperatures, is dangerous and difficult. Sodium coolant flowing in the reactor pool-type configuration induces abundant new phenomena, such as thermal stratification (Wu et al, 2020), thermal striping, thermal fatigue, and gas entrainment which influence the temperature measurements, in-pile components stress, vessel structural integrity, and natural circulation capacity (Ono et al, 2016). The development of mathematic models, calculation algorithms, analysis code, and V&V experiments (Kim et al, 2016) for the above phenomena in SFR is an urgent issue.…”

Section: Sodium-cooled Fast Reactormentioning

confidence: 99%

Grand challenges in advanced nuclear reactor design

Tian

2022

Front. Nucl. Eng.

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Section: Sodium-cooled Fast Reactormentioning

confidence: 99%

Grand challenges in advanced nuclear reactor design

Tian

2022

Front. Nucl. Eng.

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“…The initial condition and boundary condition for transient analysis refer to the previous data set obtained from the sodium experiment by the PLANDTL (Ono, 2016). The PLANDTL had the simulated core which consists of the 7 simulated subassemblies.…”

Section: Transient Analysismentioning

confidence: 99%

“…It is needed to predict the thermal-hydraulic in the plant not only under the normal operating conditions but also under the severe accident (Kamide, 2017a;Kamide, 2017b). Japan Atomic Energy Agency (JAEA) is implementing the experimental and numerical study on thermal-hydraulics for the sodium-cooled fast reactor plant to establish the evaluation method based on the numerical simulation to confirm the coolability of the decay heat removal system (DHRS) which is driven by the natural circulation under both the normal operating condition and the severe accident conditions Kamide, 2001;Kamide, 2011;Ono, 2016;Watanabe, 2015). The sodium test loop, the PLANDTL-2, was built to investigate the thermal-hydraulics in the sodium-cooled fast reactor, which consists of the simulated core, two types of decay heat removal system, the secondary loop, the air coolers.…”

Section: Introductionmentioning

confidence: 99%

Preliminary analysis of sodium experimental apparatus PLANDTL-2 for development of evaluation method for thermal-hydraulics in reactor vessel of sodium fast reactor under decay heat removal system operation condition

Ono

Tanaka

Miyake

et al. 2020

Mechanical Engineering Journal

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Fully natural circulation decay heat removal systems (DHRSs) are adopted for sodium fast reactors, which is a passive safety feature without any electrical pumps. It is needed to grasp the thermal-hydraulic phenomena in the reactor vessel and evaluate the coolability of the core under the natural circulation not only for the normal operating condition but also for severe accident conditions. In this paper, the numerical results of the preliminary analysis for the sodium experimental condition with the PLANDTL-2, in which the core and the upper plenum with a dipped-type direct heat exchanger (DHX) were modeled, are discussed to establish an appropriate numerical models for the reactor core including the gap region among the subassemblies and the DHX. The transient analysis simulating the reactor scram reveals that the 3-dimensional large scale flow structure is developed through the gaps in the whole of the core area during the reactor scram. The steady-state analysis coinciding Richardson number between the PLANDTL-2 and the reactor operation condition reveals that the hot spot and cold spot appear depending on the location of the DHX, which is caused by the complex thermalhydraulic phenomena driven by the natural circulation. From these preliminary analyses, the characteristics of the thermal-hydraulics behavior in the PLANDTL-2 to be focused are extracted.

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