Research on the structure design of the LBE reactor coolant pump in the lead base heap

Lu, Yonggang; Zhu, Rong; Wang, Xiuli; An, Ce; Chen, Jing

doi:10.1016/j.net.2018.09.023

Cited by 26 publications

(8 citation statements)

References 3 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…It was found that the dynamic event tree (DET) analysis produced results were less conservative than those obtained in NUREG-1150, which had predicted larger leak rates earlier in the accident. Lu Y. et al [16][17][18] studied the third and fourth generation reactor coolant pumps, main including gas-liquid two-phase flow and the transient characteristics of pump under extreme operating conditions, and finding in different gas fraction conditions, the homogeneous distribution of gas phase component in the fluid area was mainly related to the operating condition of pump, and when the volume flow rate deviates from the designed operating point, the fluid medium's gas phase and liquid phase will separate to some extent.…”

Section: Introductionmentioning

confidence: 99%

Mathematical Modelling Forecast on the Idling Transient Characteristic of Reactor Coolant Pump

Wang

Xie

et al. 2019

Processes

View full text Add to dashboard Cite

The idling behavior of the reactor coolant pump is referred to as an important indicator of the safe operation of the nuclear power system, while the idling transition process under the power failure accident condition is developed as a transient flow process. In this process, the parameters such as the flow rate, speed, and head of the reactor coolant pump are all nonlinear changes. In order to ensure the optimal idling behavior of the reactor coolant pump under the power cutoff accident condition, this manuscript takes the guide vanes of the AP1000 reactor coolant pump as the subject of this study. In this paper, the mathematical model of idling speed and flow characteristic curve of reactor coolant pump under the power failure condition were proposed, while the hydraulic modeling database of different vane structure parameters was modeled based on the orthogonal optimization schemes. Furthermore, based on the mathematical modeling framework of multiple linear regressions, the mathematical relationship of the hydraulic performance of each guide vane in different parameters was predicted. The derived model was verified with the idling test data.

show abstract

Section: Introductionmentioning

confidence: 99%

Mathematical Modelling Forecast on the Idling Transient Characteristic of Reactor Coolant Pump

Wang

Xie

et al. 2019

Processes

View full text Add to dashboard Cite

show abstract

“…However, the cavitation evolution of the nuclear reactor coolant pump impeller in different cavitation and the radial force and axial force variation on the impeller are seldom studied, especially the effect of the eccentric distance of the impeller on the nuclear reactor coolant pump in different cavitation states [17]. Lu Y. et al studied the third and fourth generation reactor coolant pumps, main including gas-liquid two-phase flow and the transient characteristics of pump under extreme operating conditions, and finding in different gas fraction conditions, the homogeneous distribution of gas phase component in the fluid area was mainly related to the operating condition of pump, and when the volume flow rate deviates from the designed operating point, the fluid medium's gas phase and liquid phase will separate to some extent [18][19][20].…”

Section: Introductionmentioning

confidence: 99%

Influence of Eccentricity on Hydrodynamic Characteristics of Nuclear Reactor Coolant Pump under Different Cavitation Conditions

et al. 2020

Self Cite

View full text Add to dashboard Cite

In order to study the influence of eccentricity on hydrodynamic characteristics of nuclear reactor coolant pump under different cavitation conditions, five different schemes were obtained by analyzing and optimizing the existing structural schemes. Based on the RNG k-ε model (Renormalization Group with k-epsilon turbulence models) and two-fluid two-phase flow model, the unsteady numerical analysis and test verification of different designed schemes are carried out by using the flow field software ANSYS CFX. The results of research show that different eccentricities will affect the nuclear reactor coolant pump’s head under different cavitation conditions, and the corresponding head in the scheme with the eccentricity of 5mm under the fracture cavitation condition is lower than that of the other schemes. When the impeller rotates at a certain angle from the initial position under critical and severe cavitation conditions, the radial force acting on the rotor system will fluctuate greatly. Under the condition of fracture cavitation, the radial force changed periodically and the resultant force value is small. Compared to the original scheme, the peak value of radial force is 6° clockwise after eccentricity of the impeller appeared. With the aggravation of cavitation condition, the axial force value of impeller decreases, but the corresponding amplitude of the impeller increases. Under critical and severe cavitation conditions, the maximum axial force amplitude of the nuclear reactor coolant pump appears in the two times blade frequency, and in the broken cavitation condition, the maximum axial force amplitude appears at the shaft frequency. When the eccentricity is 20 mm, the axial force fluctuates most under critical and severe cavitation conditions, and when the eccentricity is 10 mm, the corresponding axial force is smaller than that of the original scheme. When the eccentricity is 5 mm, the axial force on the impeller is the smallest, but the amplitude is the largest under the condition of fracture cavitation.

show abstract

“…In 2017, according to FT‐4 test facility, Beznosov et al 15 carried out experiment studies on the axial lead coolant pump performance with different blade parameters. In 2018, Lu et al 16 designed and did numerically studied on a centrifugal LBE coolant pump for SVBR reactor, and tested the performance of the pump based on water. Shi et al 17 experimentally investigated the gas lift pump for the lead‐bismuth eutectic loop by natural circulation capability loop (NCCL) test facility.…”

Section: Introductionmentioning

confidence: 99%

Design and hydraulic performance studies on an axial lead‐bismuth pump for GEN‐IV reactors

Wang

et al. 2020

Int J Energy Res

View full text Add to dashboard Cite

Summary Lead or lead‐alloy‐cooled fast reactors (LFRs) have been proved to be the most promising generation IV reactors with high performance in neutron economy, thermal hydraulics and security features. When lead‐bismuth eutectic (LBE) is used as coolant for LFR, the primary LBE pump is a key conveying equipment in LFRs, because it pumps liquid LBE to remove decay heat produced by core. The hydraulic performance and coolant flow velocity of LBE coolant pump is of great importance for the safety aspects concerning LFRs. This study aims to design an axial LBE pump firstly based on the theory of planar cascade and streamline method, then establishes three‐dimensional model of the axial LBE pump and performs the simulation analysis based on Ansys CFX software to study the impact of design parameters on LBE pump hydraulic performance. The results show that the highest flow velocity occurs at the blade of pump and it increases with the rotating speed, while the pump efficiency and pump head appear up‐down tendency as the flow rate increasing. The optimum rotating speed and the corresponding impeller parameters are proposed based on the theoretic and numerical studies. The research work will provide a theoretical basis and referred solution for the design of primary pump small module LFRs.

show abstract

Research on the structure design of the LBE reactor coolant pump in the lead base heap

Cited by 26 publications

References 3 publications

Mathematical Modelling Forecast on the Idling Transient Characteristic of Reactor Coolant Pump

Mathematical Modelling Forecast on the Idling Transient Characteristic of Reactor Coolant Pump

Influence of Eccentricity on Hydrodynamic Characteristics of Nuclear Reactor Coolant Pump under Different Cavitation Conditions

Design and hydraulic performance studies on an axial lead‐bismuth pump for GEN‐IV reactors

Contact Info

Product

Resources

About