CFD Analysis of the Primary Cooling System for the Small Modular Natural Circulation Lead Cooled Fast Reactor SNRLFR-100

Zhao, Pengcheng; Shi, Kangli; Li, Shuzhou; Feng, Jianmei; Chen, Hongli

doi:10.1155/2016/9612120

Cited by 5 publications

(5 citation statements)

References 14 publications

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“…It is expected that reactor cooling systems (e.g., pressurized water reactor, small modular reactor) have unidentical mass flow rate in the similar sections within the core [34,35]. It is also expected to find the same hydraulic behavior in the case of the dual fluid reactor due to the same reasons.…”

Section: Global Characteristicsmentioning

confidence: 99%

Numerical Study of Flow and Heat Transfer Characteristics in a Simplified Dual Fluid Reactor

El‐Gendy

Czerski

2023

Energies

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This study presents the design and computational fluid dynamics (CFD) analysis of a mini demonstrator for a dual fluid reactor (DFR). The DFR is a novel concept currently under investigation. The DFR is characterized by the implementation of two distinct liquid loops dedicated to fuel and coolant. It integrates the principles of molten salt reactors and liquid metal cooled reactors; thus, it operates in a high temperature and fast neutron spectrum, presenting a distinct approach in the field of advanced nuclear reactor design. The mini demonstrator serves as a scaled-down version of the actual reactor, primarily aimed at gaining insights into the CFD analysis intricacies of the reactor while minimizing computational costs. The CFD modeling of the MD intends to add valuable data for the purpose of modeling validation against experiments to be conducted on the MD. These experiments can be used for DFR licensing and design optimization. The coolant and fuel utilized in the mini demonstrator are of low Prandtl number (Pr = 0.01) liquid lead, operating at two distinct inlet temperatures, namely 873 K and 1473 K. The study showed a rapid increase in turbulence due to intense mixing and abrupt changes in flow areas and directions, despite the relatively low inlet velocities. Hot spots characterized by elevated temperatures were identified, analyzed, and justified based on their spatial distribution and flow conditions. Flow swirling within pipes was identified and a remedy approach was suggested. Inconsistent mass flow rates were observed among the fuel pipes, with higher rates observed in the lateral pipes. Although lower fuel temperatures were observed in the lateral pipes, they consistently exhibited higher heat exchange characteristics. The study concludes by giving physical insights into the heat transfer and flow behavior, and proposing design considerations for the dual fluid reactor to enhance structural safety and durability, based on the preliminary analysis conducted.

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Section: Global Characteristicsmentioning

confidence: 99%

Numerical Study of Flow and Heat Transfer Characteristics in a Simplified Dual Fluid Reactor

El‐Gendy

Czerski

2023

Energies

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“…Pool-type reactor [10] A reactor with a cylindrical shaped tank that immerses its core in an open pool of water Water Gas-cooled reactor [11] A reactor that uses graphite as moderator and gas as its coolant Helium gas Liquid metal cooled reactor [12] A reactor that uses liquid metal as primary coolant lead-bismuth eutectic…”

Section: Light Watermentioning

confidence: 99%

A review on predictive maintenance technique for nuclear reactor cooling system using machine learning and augmented reality

Nor

Kassim

Minhat

et al. 2022

IJECE

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<span lang="EN-US">Reactor TRIGA PUSPATI (RTP) is the only research nuclear reactor in Malaysia. Maintenance of RTP is crucial which affects its safety and reliability. Currently, RTP maintenance strategies used corrective and preventative which involved many sensors and equipment conditions. The existing preventive maintenance method takes a longer time to complete the entire system’s maintenance inspection. This study has investigated new predictive maintenance techniques for developing RTP predictive maintenance for primary cooling systems using machine learning (ML) and augmented reality (AR). Fifty papers from recent referred publications in the nuclear areas were reviewed and compared. Detailed comparison of ML techniques, parameters involved in the coolant system and AR design techniques were done. Multiclass support vector machines (SVMs), artificial neural network (ANN), long short-term memory (LSTM), feed forward back propagation (</span><span lang="EN-US">FFBP), graph neural networks-feed forward back propagation (GNN-FFBP) and ANN were used for the machine learning techniques for the nuclear reactor. Temperature, water flow, and water pressure were crucial parameters used in monitoring a nuclear reactor. Image marker-based techniques were mainly used by smart glass view and handheld devices. A switch knob with handle switch, pipe valve and machine feature were used for object detection in AR markerless technique. This study is significant and found seven recent papers closely related to the development of predictive maintenance for a research nuclear reactor in Malaysia.</span>

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“…SNCLFR-100 uses pure melted lead as primary coolant by means of natural circulation, the rated thermal power of SNCLFR-100 is 100 MW and the refueling interval is 10 years without assembly reconfiguration. SNCLFR-100 is a typical pool-type reactor with an array of heterogeneous square fuel assemblies loaded with MOX fuels (Zhao et al, 2016;Shi et al, 2018). The overall structure design of SNCLFR-100 primary cooling system and fuel assembly are shown in Figure 1, and the main design parameters are listed in Table 1.…”

Section: Snclfr-100 Reactor Designmentioning

confidence: 99%

“…In United States, A series of natural circulation LFR conceptual design were carried out by Argonne National Laboratory (ANL) and Lawrence Livermore National Laboratory (LLNL), such as SSTAR (Bortot et al, 2011), SUPERSTAR (Koo et al, 2007), STAR-LM (Hong et al, 2005), and ENHS (Wu, 2016). In China, a 100 MWth lead-cooled small modular reactor named SNCLFR-100 with a passive cooling feature to both normal and abnormal operations, was proposed by University of Science and Technology of China (USTC) (Chen et al, 2016;Zhao et al, 2016).…”

Section: Introductionmentioning

confidence: 99%

Safety Analysis of Small Modular Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100 Under Unprotected Transient

et al. 2021

Self Cite

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SNCLFR-100 is a small modular natural circulation lead-cooled fast reactor, developed by University of Science and Technology of China, aiming at taking full advantage of the good economics and inherent safety of lead-cooled fast reactors to develop miniaturized, lightweight and multi-purpose special nuclear reactor technology. SNCLFR-100 is still in the conceptual design stage, in order to fully evaluate the safety features of the reactor and provide reference for the optimization design of the next stage, three typical transients are selected based on the analysis of the SNCLFR-100 initiating events by using the code Analysis of Thermal-hydraulics of Leaks and Transients (ATHLET), which are unprotected transient overpower (UTOP), unprotected loss of heat sink (ULOHS) and unprotected partial blockage in the hottest fuel assembly. For UTOP, the unexpected positive reactivity insertion of 0.7$ in 15s led to two large power peaks in the core quickly, and then the core power began to decrease and gradually stabilized under the action of various of negative feedbacks of the reactor, the peak temperatures of fuel and cladding rose rapidly with the increase of core power and eventually stabilized at a higher temperature. For ULOHS, as the reactor were driven by natural circulation, the coolant mass flow rate continued to decline after the transient, both core and cladding temperatures rose quickly and the temperature rise were smaller than that of UTOP transient, the reactor shutdown by itself and the peak temperatures of fuel and cladding were smaller than the safety limit. For unprotected partial blockage in the hottest fuel assembly, with the increase of the blockage rate of the hottest fuel assembly inlet, the coolant flow rate, the peak temperatures of coolant, fuel and cladding increased significantly, when the blockage rate increased to 0.9, the coolant flow rate of the hottest fuel assembly dropped to about 12.6% of the normal value, and the cladding peak temperature would exceed the cladding melting point, measures should be taken to avoid the happening of severe accident.

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CFD Analysis of the Primary Cooling System for the Small Modular Natural Circulation Lead Cooled Fast Reactor SNRLFR-100

Cited by 5 publications

References 14 publications

Numerical Study of Flow and Heat Transfer Characteristics in a Simplified Dual Fluid Reactor

Numerical Study of Flow and Heat Transfer Characteristics in a Simplified Dual Fluid Reactor

A review on predictive maintenance technique for nuclear reactor cooling system using machine learning and augmented reality

Safety Analysis of Small Modular Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100 Under Unprotected Transient

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