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  • Open Access

    ARTICLE

    Analysis of Rotor-Seizure-Induced Pressure Rise in a Nuclear Reactor Primary Cooling Loop

    Haoyu Cui1, Congxin Yang1,2,*, Yanlei Guo1, Tianzhi Lv1, Sen Zhao1

    FDMP-Fluid Dynamics & Materials Processing, Vol.20, No.12, pp. 2907-2926, 2024, DOI:10.32604/fdmp.2024.055301 - 23 December 2024

    Abstract Most of existing methods for the safety assessment of the primary cooling loop of nuclear reactors in conditions of reactor coolant pump (RCP) failure (rotor seizure accident) essentially rely on the combination of one-dimensional theory and experience. This study introduces a novel three-dimensional model of the ‘Hualong-1’ (HPR1000) primary loop and uses the method of matching the resistance characteristics of the tube to ensure that the main pump operates at the rated operating condition. In particular, the three-dimensional unsteady numerical calculation of the RCP behavior in the rotor-seizure accident condition is carried out in the More >

  • Open Access

    ARTICLE

    Transient Analysis of a Reactor Coolant Pump Rotor Seizure Nuclear Accident

    Mengdong An1, Weiyuan Zhong1, Wei Xu2, Xiuli Wang1,*

    FDMP-Fluid Dynamics & Materials Processing, Vol.20, No.6, pp. 1331-1349, 2024, DOI:10.32604/fdmp.2023.046604 - 27 June 2024

    Abstract The reactor coolant pump (RCP) rotor seizure accident is defined as a short-time seizure of the RCP rotor. This event typically leads to an abrupt flow decrease in the corresponding loop and an ensuing reactor and turbine trip. The significant reduction of core coolant flow while the reactor is being operated at full load can have very negative consequences. This potentially dangerous event is typically characterized by a complex transient behavior in terms of flow conditions and energy transformation, which need to be analyzed and understood. This study constructed transient flow and rotational speed mathematical More > Graphic Abstract

    Transient Analysis of a Reactor Coolant Pump Rotor Seizure Nuclear Accident

  • Open Access

    ARTICLE

    Influence of the Impeller/Guide Vane Clearance Ratio on the Performances of a Nuclear Reactor Coolant Pump

    Xiaorui Cheng1,2,*, Xiang Liu1, Boru Lv1

    FDMP-Fluid Dynamics & Materials Processing, Vol.18, No.1, pp. 93-107, 2022, DOI:10.32604/fdmp.2022.017566 - 10 November 2021

    Abstract An AP1000 nuclear reactor coolant pump is considered to assess the influence of the Impeller/Guide vane clearance on the performances of this type of pumps. Experiments and numerical simulations relying on an unidirectional fluid-solid coupling approach are used to investigate the problem (stress, strain and mode of the rotor). The results reveal the relationship existing between the hydraulic performance of the nuclear reactor coolant pump and the clearance ratio. The effect of clearance ratio on the maximum equivalent stress on the back surface of the impeller blade is greater than that on the working surface More >

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