Stability analysis of nuclear-coupled thermal hydraulics for a natural circulation lead-cooled fast reactor

Lu, Qiyue; Rizwan-uddin,

doi:10.1016/j.anucene.2020.107747

Cited by 7 publications

(2 citation statements)

References 13 publications

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“…[31]. Lu and Rizwan-uddin [32] carried out an extensive stability analysis of natural circulation in lead cooled fast reactor accounting for both the thermal-hydaulics and neutronics using a 1-D model. Saha et al [33] conducted the symbolic time series analysis to predict the flow reversal in NCL systems employing a 1-D NCL model accounting for the wall effects.…”

Section: Chaotic Oscillations and Stability Analysis Of Ncl Systemsmentioning

confidence: 99%

Stability analysis of a single-phase rectangular Coupled Natural Circulation Loop system employing a Fourier series based 1-D model

Dass,

Gedupudi

2020

Preprint

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A linear stability analysis of a single-phase Coupled Natural Circulation Loop (CNCL) is carried out using a Fourier series based 1-D model. A 3-D CFD study is undertaken to assess the ability of the 1-D model to capture the nonperiodic oscillatory behaviour exhibited by the CNCL system. After the model verification, the stability maps of the system are obtained from the eigenvalues of the steady-state. The CNCL has multiple steady states and the stability maps of consistently observed steady states are presented. A thorough parametric study is conducted to observe the influence of non-dimensional numbers on the CNCL system. Increase in the Fourier number and flow resistance coefficient lead to an increase in the domain of stability. A comparison of the linear stability map with the empirical stability map indicates that the non-linear terms do not significantly affect the stability boundary.

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Section: Chaotic Oscillations and Stability Analysis Of Ncl Systemsmentioning

confidence: 99%

Stability analysis of a single-phase rectangular Coupled Natural Circulation Loop system employing a Fourier series based 1-D model

Dass,

Gedupudi

2020

Preprint

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“…Supercritical water-cooled reactor (SCWR) is the generation IV nuclear reactor that uses water as a coolant (Was et al, 2007;Wang et al, 2022;Lu, 2020;Tan et al, 2013). In SCWR, the coolant temperature at outlet position is designed to be 550°C and the pressure is 25 MPa, which exceeds the thermodynamic critical point of water (374°C, 22.1 MPa), so the coolant is converted to supercritical water (SCW) in the operating state (Zinkle and Was, 2013;Chen et al, 2022aChen et al, , 2022b.…”

Section: Introductionmentioning

confidence: 99%

Oxidation behavior of the T91 ferritic/martensitic steel and 304 austenitic stainless steel in supercritical water

An²,

Wang³

2023

ACMM

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Purpose This study aims to report the oxidation behaviors of the T91 ferritic/martensitic steel (T91 steel) and 304 austenitic stainless steel (304 steel) in supercritical water (SCW) at 600°C. Design/methodology/approach The microstructure, elemental distribution and phase structure of the oxidation layers derived from the corrosion of the T91 steel and 304 steel were analyzed by scanning electron microscopy, Oxford Instrument X-ray spectroscopy, electron scattered diffraction and transmission electron microscopy. Findings The oxidation layers on the T91 steel and 304 steel have duplex structure. The two steels all suffer internal oxidation, and the phase of the internal oxidation layers are indexed as Fe-Cr spinel, although their morphologies are different. The formation of a continuous Cr-rich layer is not detected because of the relatively low Cr content of the steels, which is attributed to the corrosion property. Originality/value The accelerated corrosion and corrosion mechanism of the T91 steel and 304 steel with low Cr occurring in SCW at 600°C was clarified.

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Rotor dynamic analysis of the vertical hydro-hybrid bearing rotor coupled system of a two-circuit main loop liquid Sodium pump system

Xie

Zhu

2021

Annals of Nuclear Energy

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Stability analysis of nuclear-coupled thermal hydraulics for a natural circulation lead-cooled fast reactor

Cited by 7 publications

References 13 publications

Stability analysis of a single-phase rectangular Coupled Natural Circulation Loop system employing a Fourier series based 1-D model

Stability analysis of a single-phase rectangular Coupled Natural Circulation Loop system employing a Fourier series based 1-D model

Oxidation behavior of the T91 ferritic/martensitic steel and 304 austenitic stainless steel in supercritical water

Rotor dynamic analysis of the vertical hydro-hybrid bearing rotor coupled system of a two-circuit main loop liquid Sodium pump system

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