Nonlinear analysis of nuclear coupled density wave instability in time domain for a boiling water reactor core undergoing core-wide and regional modes of oscillations

Dutta, Goutam; Doshi, J. B.

doi:10.1016/j.pnucene.2009.04.005

Cited by 21 publications

(5 citation statements)

References 15 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The 1-D model is developed in-house. It was earlier used to simulate boiling water reactors (BWR) [19], and was extended and validated for SCWRs in the previous study [18]. Several parameters, which were earlier proposed to predict the occurrence of DHT are tested in the present study to verify their applicability in different working regimes and are also used to predict the occurrence of the deteriorated heat transfer zone (DHTZ) inside the channel.…”

Section: Introductionmentioning

confidence: 99%

Numerical Investigations Of Deteriorated Heat Transfer Phenomenon For Supercritical Water Flow In Vertical Tubes

Maitri¹,

Han²,

Zhang³

et al. 2021

Progress in Canadian Mechanical Engineering. Volume 4

View full text Add to dashboard Cite

The present paper is aimed at the in-depth thermalhydraulic analysis of supercritical water flow at various operating conditions in vertical circular tubes. A onedimensional thermal-hydraulic solution algorithm has been used for the analysis in this paper. Nine experimental cases are studied thoroughly and out of these, four cases which are operated at various working regimes are chosen and presented for the detailed analysis of deteriorated heat transfer and normal heat transfer cases. The studies are carried out for the distributions of nondimensional acceleration and buoyancy parameters, and different types of pressure drops along the axial direction and its effect on the heat transfer.

show abstract

Section: Introductionmentioning

confidence: 99%

Numerical Investigations Of Deteriorated Heat Transfer Phenomenon For Supercritical Water Flow In Vertical Tubes

Maitri¹,

Han²,

Zhang³

et al. 2021

Progress in Canadian Mechanical Engineering. Volume 4

View full text Add to dashboard Cite

show abstract

“…THRUST is developed under one dimensional flow assumption, i.e., considering the axial variation of flow and thermodynamic properties and taking the spatial mean average of field variables along the radial and azimuthal directions. THRUST developed in this work is based on the model by Dutta and Doshi [16] which was used to simulate BWRs using the homogeneous flow assumption. The model is based on the non-linear mass, momentum and energy conservation equations which are solved in the timedomain.…”

Section: Introductionmentioning

confidence: 99%

Analysis of flow induced density wave oscillations in the CANDU supercritical water reactor

Dutta

Zhang

Jiang

2015

Nuclear Engineering and Design

Self Cite

View full text Add to dashboard Cite

In this paper, a 1-D thermal-hydraulic model, THRUST, is developed to simulate and analyze the CANDU supercritical water reactor (SCWR) from the thermodynamic point of view without considering the effect of neutronic coupling. THRUST, where a characteristic-based finite difference scheme is used, is validated against the available numerical results. The model is, then, used for the analysis of the CANDU SCWR with a primary focus to determine the conditions for potential density wave oscillations. Extensive numerical studies are performed to obtain the marginal stability boundary in the operating regime of the reactor. The effect of various parameters, such as, mass flow rate, operating pressure, axial heat flux profile, local pressure drop coefficient, and friction factor, on the stability thresholds of the reactor have been investigated.

show abstract

“…The in-house 1-D Thermal-Hydraulic solveR Undertaking Supercritical waTer (THRUST), which is an extension of an earlier version used for simulating boiling water reactor (BWR) (Dutta and Doshi, 2009), is used for the simulation of the SCWR in the present work. It is based on mass, momentum and energy conservation equations and includes the thermodynamic equation of state to take care of the property changes due to the pressure and temperature.…”

Section: Introductionmentioning

confidence: 99%

Numerical models to predict steady and unsteady thermal-hydraulic behaviour of supercritical water flow in circular tubes

Dutta¹,

Maitri²,

Zhang³

et al. 2015

Nuclear Engineering and Design

Self Cite

View full text Add to dashboard Cite

. (2015). Numerical models to predict steady and unsteady thermalhydraulic behaviour of supercritical water flow in circular tubes. Nuclear Engineering and Design, 289, 155-165. DOI: 10.1016/j.nucengdes.2015.04.028 General rights Copyright and moral rights for the publications made accessible in the public portal are retained by the authors and/or other copyright owners and it is a condition of accessing publications that users recognise and abide by the legal requirements associated with these rights.• Users may download and print one copy of any publication from the public portal for the purpose of private study or research.• You may not further distribute the material or use it for any profit-making activity or commercial gain • You may freely distribute the URL identifying the publication in the public portal ? Take down policyIf you believe that this document breaches copyright please contact us providing details, and we will remove access to the work immediately and investigate your claim. • The supercritical flows with the normal heat transfer and deteriorated heat transfer are simulated.• The numerical results are compared with the experimental data and the errors are reported.• The transient simulations are also carried out using the CFD and THRUST.• The transient results obtained using the CFD and THRUST are compared under different conditions. a r t i c l e i n f o t r a c tThe present paper is aimed at the development of numerical models to predict steady and unsteady thermal-hydraulic behaviour of supercritical water flow at various operating conditions. A simple onedimensional numerical thermal-hydraulic model based on a finite-difference scheme has been developed. A detailed CFD analysis based on two turbulence models, Reynolds Stress Model and k-ω SST model, has also been presented in this paper. Seven experimental cases of steady state and vertically up flowing supercritical water in circular tubes operated at various working regimes, such as normal and deteriorated heat transfer regions, are used to validate the numerical models. Comparisons for steady state flow show good agreement between the numerical and experimental results for all normal heat transfer cases and most of the deteriorated heat transfer cases. Next, the numerical models are used for transient simulations. Three case studies are undertaken with a purpose to quantify the time dependent responses from both the 1-D model and CFD model. The comparisons carried out for both the normal and deteriorated heat transfer conditions show a good agreement between the two numerical models.

show abstract

Nonlinear analysis of nuclear coupled density wave instability in time domain for a boiling water reactor core undergoing core-wide and regional modes of oscillations

Cited by 21 publications

References 15 publications

Numerical Investigations Of Deteriorated Heat Transfer Phenomenon For Supercritical Water Flow In Vertical Tubes

Numerical Investigations Of Deteriorated Heat Transfer Phenomenon For Supercritical Water Flow In Vertical Tubes

Analysis of flow induced density wave oscillations in the CANDU supercritical water reactor

Numerical models to predict steady and unsteady thermal-hydraulic behaviour of supercritical water flow in circular tubes

Contact Info

Product

Resources

About