Partial flow blockage analysis of the hottest fuel assembly in SNCLFR-100 reactor core

Shi, Kangli; Li, Shuzhou; Zhang, Xilin; Zhao, Pengcheng; Chen, Hongli

doi:10.1007/s41365-017-0351-3

Cited by 9 publications

(3 citation statements)

References 16 publications

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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%

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

et al. 2021

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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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Section: Snclfr-100 Reactor Designmentioning

confidence: 99%

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

et al. 2021

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“…In China, under the support of the Chinese ADS project, CLEAR‐I, a 10 MWt lead‐cooled reactor has been developed . Besides, a small modular natural circulation lead‐cooled reactor (SNCLFR‐100) is being developed by researchers in the University of Science and Technology of China (USTC), and investigations into its neutronic performance, system safety, and accident analysis have been conducted . Recently, Zhou et al proposed a concept for a 20 MWt innovative small transportable LBE cooled reactor named SPARK, which can achieve a core lifetime of 20 years …”

Section: Introductionmentioning

confidence: 99%

“…14 Besides, a small modular natural circulation lead-cooled reactor (SNCLFR-100) is being developed by researchers in the University of Science and Technology of China (USTC), 15 and investigations into its neutronic performance, system safety, and accident analysis have been conducted. 16,17 Recently, Zhou et al proposed a concept for a 20 MWt innovative small transportable LBE cooled reactor named SPARK, which can achieve a core lifetime of 20 years. 18 Based on the experiences of existing lead-based SMRs, an improved 300 MWt lead-bismuth SMR, LESMOR, with advanced (Th + Pu) N fuel was studied in this paper to obtain improved neutronic/thermal-hydraulic features, including core lifetime and safety performance.…”

Section: Introductionmentioning

confidence: 99%

Neutronic/thermal‐hydraulic design features of an improved lead‐bismuth cooled small modular fast reactor

et al. 2019

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Summary Lead‐based fast reactors (LFRs) have unique advantages in the development of a SMR, which has attracted a lot of attention in recent years. In this paper, an optimized design for a lead‐bismuth small modular reactor was studied on the basis of the design of SUPERSTAR. This paper aims to propose an improved LFR core scheme to enhance the neutronic performance as well as the thermal‐hydraulic safety of the reference reactor. Advanced nitride fuel is adopted in which the plutonium is used as the driven fuel, while thorium is used as the fertile fuel. Subchannel analysis was performed in the assembly design using an in‐house subchannel code, SUBAS, and an 11 × 11 scheme with a pitch‐to‐diameter (P/D) ratio of 1.4 was chosen. Using the modified assembly, the core was redesigned using the coupled code MCORE. The active core was divided into four zones with different enrichment of 239Pu to extend the core lifetime and flatten the power distribution. The main kinetic parameters and reactivity coefficients were obtained. Neutronic performance at different operation times was also studied. The maximum radial power peak factor was 1.28, while the maximum total power peak factor was 1.737. During the whole lifetime, the reactivity swing was 0.926$, which was below the limit of 1$. The subchannel study of the core flow distribution showed that a flow distributor is needed to further improve the flow distribution capability. The peaking cladding temperature was 508.7°C, and the maximum fuel center temperature was 723.4°C, both of which do not exceed the limit temperature. Compared with features of SUPERSTAR, the peaking cladding temperature was well improved and the lifetime extended.

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Seismic and stress qualification of LMFR fuel rod and simple method for the determination of LBE added mass effect

et al. 2019

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Partial flow blockage analysis of the hottest fuel assembly in SNCLFR-100 reactor core

Cited by 9 publications

References 16 publications

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

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

Neutronic/thermal‐hydraulic design features of an improved lead‐bismuth cooled small modular fast reactor

Seismic and stress qualification of LMFR fuel rod and simple method for the determination of LBE added mass effect

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