Analysis of flow induced density wave oscillations in the CANDU supercritical water reactor
01 May 2015-Nuclear Engineering and Design (North-Holland)-Vol. 286, pp 150-162
TL;DR: 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.
About: This article is published in Nuclear Engineering and Design.The article was published on 2015-05-01 and is currently open access. It has received 25 citations till now. The article focuses on the topics: Heat flux & Supercritical fluid.
TL;DR: A systematic overview of all key two-phase instabilities focusing on the fundamental mechanisms leading to their occurrence is provided, with emphasis on how these mechanisms may change depending on whether flow may be classified as macro- or micro-channel.
TL;DR: In this article, the authors investigated the parallel channel density wave instability in the CANDU supercritical water reactor (SCWR) using a 1-D thermal-hydraulic model in the time domain.
TL;DR: In this paper, a thermal-hydraulic (TH) model is employed to solve the nonlinearly coupled mass, axial momentum and energy conservation equations in a time domain using characteristics based implicit finite difference scheme accounting for the compressible flow dynamics of supercritical water.
Abstract: The present study numerically investigates Density wave oscillations (DWOs), a dynamic instability and captures Heat transfer deterioration (HTD) phenomenon for a Supercritical water reactor (SCWR) of the U. S. reference design. A Thermal-hydraulic (TH) model is employed to solve the nonlinearly coupled mass, axial momentum and energy conservation equations in a time domain using characteristics based implicit finite difference scheme accounting for the compressible flow dynamics of supercritical water. The analysis of DWOs is carried out to obtain the marginal stability thresholds. Next, the steady as well as transient safety analyses are carried out to determine the occurrence of HTD, access its severity and identify the safe operating conditions. Finally, the common operating conditions are predicted where the U. S. SCWR will be stable as well as safe.
TL;DR: A 3D numerical study of turbulent flow of supercritical water flowing upward in two heated parallel channels with constant applied wall heat flux was developed using a RANS model in the Computational Fluid Dynamics (CFD) code ANSYS CFX as discussed by the authors.
TL;DR: In this article, the existence of Ledinegg and dynamic instability phenomena in a rectangular shape of a natural circulation loop at supercritical condition using supercritical water as a working fluid.
TL;DR: In this paper, the authors identify the causes and mechanisms of thermal-hydrodynamic instabilities in boiling flow in a water-cooled reactor, an evaporator, or an electronic cooling system.
TL;DR: In this paper, two new correlations of single-phase friction factor for turbulent flow are proposed, one for smooth pipes and the other for both smooth and rough pipes, which is an idea replacement of the correlations of Blasius and Filonenko.
TL;DR: In this paper, the authors proposed dimensionless parameters for the analysis of stability in heated channels with supercritical fluids, based on the classical phase change and sub-cooling numbers adopted in the case of boiling channels, proposing a novel formulation making use of fluid properties at the pseudocritical temperature as a function of pressure.
TL;DR: A review of the current state of the art on the topic of coupled neutronic-thermohydraulic instabilities in boiling water nuclear reactors (BWRs) can be found in this article.
TL;DR: In this article, supercritical flow stability in a single-channel, natural-convection loop is examined using a non-linear numerical code and a theoretical stability criterion is also developed to verify the numerical prediction.