Analysis of passive residual heat removal system in AP1000 nuclear power plant

Sierchuła, Jakub

doi:10.1088/1755-1315/214/1/012095

Cited by 8 publications

(3 citation statements)

References 5 publications

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“…Similarly, the passive systems are used in third-generation reactors all over the world, such as AP1000 [3,4], VVER1000 [5], and APR1000 [6]. e passive safety system can not only improve the safety performance but also reduce the cost of the NPPs, making nuclear power a safer and economical choice.…”

Section: Prefacementioning

confidence: 99%

Design, Experiment, and Commissioning of the Passive Residual Heat Removal System of China’s Generation III Nuclear Power HPR1000

Chu

et al. 2021

Science and Technology of Nuclear Installations

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In response to a station blackout accident similar to the Fukushima nuclear accident, China’s Generation III nuclear power HPR1000 designed and developed a passive residual heat removal system connected to the secondary side of the steam generator. Based on the two-phase natural circulation principle, the system is designed to bring out long-term core residual heat after an accident to ensure that the reactor is in a safe state. The steady-state characteristic test and transient start and run test of the PRS were carried out on the integrated experiment bench named ESPRIT. The experiment results show that the PRS can establish natural circulation and discharge residual heat of the first loop. China’s Fuqing no. 5 nuclear power plant completed the installation of the PRS in September 2019 and carried out commissioning work in October. This debugging is the first real-world debugging of the new design. This paper introduces the design process of the PRS debugging scheme.

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Section: Prefacementioning

confidence: 99%

Design, Experiment, and Commissioning of the Passive Residual Heat Removal System of China’s Generation III Nuclear Power HPR1000

Chu

et al. 2021

Science and Technology of Nuclear Installations

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“…For example, the cooling function, and related passive decay heat removal systems, play an important role in increasing the reliability of a nuclear reactor, as highlighted by the Fukushima accident. Some advanced Generation III and III+ water reactors such as the AP1000 and the ESBWR as well as the Generation IV reactors foresee passive systems for core decay heat removal after reactor shutdown [2][3][4]. These kind of passive systems may rely on natural circulation features in order to ensure the cooling capability.…”

Section: Introductionmentioning

confidence: 99%

Modelling and CFD analysis of the DYNASTY loop facility

Nalbandyan

Cammi²,

Lorenzi³

et al. 2022

EPJ Nuclear Sci. Technol.

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In this paper, CFD assessment of the DYNASTY natural circulation loop, adopting a RANS turbulence modeling approach, is performed using the OpenFOAM open source toolbox. The DYNASTY facility is designed to investigate the stability and dynamics of heat-generating fluids, in particular molten salts, in a natural or forced circulation regime and as such, it is one-of-a-kind, large scale facility for studying the natural circulation in presence of distributed heating. In this work, a CFD model of the facility is set up and validated by comparing the model results to experimental data obtained during the initial testing campaign of the facility, with water as working fluid. In particular, the equilibrium state of the system is investigated in terms of the mass flow dynamic behaviour and the temperature difference across the cooler section of the loop. It is shown that the CFD simulations adopting the k − ω SST turbulence model best reflect the experimental results. The CFD results are also in agreement with a simplified 1D modeling as well as an analytical solution.

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“…The thermal performance is depended on mass and enthalpy equation of the coolant/moderator with one group diffusion equation of the fuel pin. Sierchula [12] studied in separate the passive containment cooling system and passive residual heat removal system for the nuclear power plant. The outcome of this study is simulating, presenting and describing some of the most important parameters in the nuclear power plant such as reactor coolant temperature and heat transfer.…”

Section: Introductionmentioning

confidence: 99%

Heat Transfer Enhancement in Subchannel Geometry of Pressurized Water Reactor Using Water-Based Yttrium Oxide Nanofluid

Redha¹,

Rashid²

2021

IJHT

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Simulation of Computational Fluid Dynamic is applied to present the thermal performance of water-based Yttrium oxide nanofluid in subchannel of pressurized water reactor (PWR) system. Thermal hydraulic aspect such as pressure drop and heat transfer are estimated in typical conditions of pressurized water with flow rates ranged (20×103≤Re≤80×103) using fresh water (0 %vol.) and different volume fraction of water-Yttrium oxide nanofluid (2 and 4% vol.) as coolant fluid. Results were obtained and compared with correlations of single-phase pressure drop and convective heat transfer for the case of fully developed turbulent flow. The addition of Yttrium oxide nanoparticles to the coolant fluid in pressurized water reactor led to increase in convective heat transfer coefficient and pressure drop. Increasing the nanoparticle volume fraction of (2 and 4% vol.) causing an increase in the average Nu by 3.46% and 7.61%, respectively. The CFD model established in ANSYS software was validated by comparing the pressure drop of CFD results with Blasius correlation and Nu with Ma¨ıga et al. correlation and gave a good agreement.

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Analysis of passive residual heat removal system in AP1000 nuclear power plant

Cited by 8 publications

References 5 publications

Design, Experiment, and Commissioning of the Passive Residual Heat Removal System of China’s Generation III Nuclear Power HPR1000

Design, Experiment, and Commissioning of the Passive Residual Heat Removal System of China’s Generation III Nuclear Power HPR1000

Modelling and CFD analysis of the DYNASTY loop facility

Heat Transfer Enhancement in Subchannel Geometry of Pressurized Water Reactor Using Water-Based Yttrium Oxide Nanofluid

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