Investigation of Water-Vapor Two-Phase Flow Characteristics in a Tight-Lattice Core by Large-Scale Numerical Simulation, (I)

Yoshida, Hiroyuki; Nagayoshi, Takuji; Ose, Yasuo; Takase, Kazuyuki; Akimoto, Hajime

doi:10.3327/taesj2002.3.233

Cited by 12 publications

(10 citation statements)

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“…A two-phase flow simulation code (TPFIT) with advanced interface tracing method has been developed at JAEA (3) . The one-fluid model based on the method of volume of fluid (VOF) (5) for description of two phase flow was adopted in the TPFIT code.…”

Section: Numerical Simulation Using Advanced Interface-tracking Methodsmentioning

confidence: 99%

“…However, in consideration of the large scale of the FLWR core with tight arrangement of fuel rods, it may be economically infeasible to perform full mock-up experiments to investigate all thermal-hydraulic characteristics in the design stage. This leads to a design method called "Design-by-Analysis" (3) . It emphasizes the role of numerical approaches.…”

Section: Introductionmentioning

confidence: 99%

“…In view of the importance of accurate prediction of cross flow between subchannels in the evaluation of the boiling transition (BT) in the FLWR core, the purpose of this study is to numerically simulate cross flow by using the TPFIT code (3) , which employs an advanced interface-tracking method, to statistically evaluate the simulation results, and to clarify the mechanisms of cross flow for later model development.…”

Section: Introductionmentioning

confidence: 99%

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Numerical Investigation of Cross Flow Phenomena in a Tight-Lattice Rod Bundle Using Advanced Interface Tracking Method

Zhang

Yoshida

Ose

et al. 2008

JPES

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In relation to the design of an innovative FLexible-fuel-cycle Water Reactor (FLWR), investigation of thermal-hydraulic performance in tight-lattice rod bundles of the FLWR is being carried out at Japan Atomic Energy Agency (JAEA). The FLWR core adopts a tight triangular lattice arrangement with about 1 mm gap clearance between adjacent fuel rods. In view of importance of accurate prediction of cross flow between subchannels in the evaluation of the boiling transition (BT) in the FLWR core, this study presents a statistical evaluation of numerical simulation results obtained by a detailed two-phase flow simulation code, TPFIT, which employs an advanced interface tracking method. In order to clarify mechanisms of cross flow in such tight lattice rod bundles, the TPFIT is applied to simulate water-steam two-phase flow in two modeled subchannels. Attention is focused on instantaneous fluctuation characteristics of cross flow. With the calculation of correlation coefficients between differential pressure and gas/liquid mixing coefficients, time scales of cross flow are evaluated, and effects of mixing section length, flow pattern and gap spacing on correlation coefficients are investigated. Differences in mechanism between gas and liquid cross flows are pointed out.

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Section: Numerical Simulation Using Advanced Interface-tracking Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Numerical Investigation of Cross Flow Phenomena in a Tight-Lattice Rod Bundle Using Advanced Interface Tracking Method

Zhang

Yoshida

Ose

et al. 2008

JPES

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“…H. Yoshida developed numerical simulation code TPFIT to simulate detailed two-phase flow behaviors in nuclear systems (Yoshida et al 2004). H. Yoshida, et al simulated rising bubble behavior under accelerating conditions by the code and validated it with the previous experimental date (Yoshida et al 2014, Mizuno et al 2012.…”

Section: Introductionmentioning

confidence: 95%

Numerical simulation of two-phase flow behavior in Venturi scrubber by interface tracking method

Horiguchi

Yoshida

Abe

2016

Nuclear Engineering and Design

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From the viewpoint of protecting a containment vessel of light water reactor and suppressing the diffusion of radioactive materials from a light water reactor, it is important to develop the device which allows a filtered venting of contaminated high pressure gas. In the filtered venting system that used in European reactors, so called Multi Venturi Scrubbers System is used to realize filtered venting without any power supply. This system is able to define to be composed of Venturi Scrubbers (VS) and a bubble column. In the VS, scrubbing of contaminated gas is promoted by both gas releases through the submerged VS and gas-liquid contact with splay flow formed by liquid suctioned through a hole provided by the pressure difference between inner and outer regions of a throat part of the VS. However, the scrubbing mechanism of the self-priming VS including effects of gas mass flow rate and shape of the VS are understood insufficiently in the previous studies. Therefore, we started numerical and experimental study to understand the detailed two-phase flow behavior in the VS. In this paper, to understand the VS operation characteristics for the filtered venting, we performed numerical simulations of two-phase flow behavior in the VS. In the first step of this study, we perform numerical simulations of supersonic flow by the TPFIT to validate the applicability of the TPFIT for high velocity flow like flow in the VS. In the second step, numerical simulation of two-phase flow behavior in the VS including selfpriming phenomena. As the results, dispersed flow in the VS was reproduced in the numerical simulation, as same as the visualization experiments.

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“…When we carry out a volume tracking simulation of a bubbly flow consisting of large and small bubbles, we may be able to assign a number of cells to a large bubble but not to a small bubble. Yoshida et al (8) have simulated a large bubble rising through stagnant water in a two by two rod bundle using a volume tracking scheme (9) . They obtained good prediction of bubble velocity (10) with a spatial resolution of d*=63.…”

Section: Introductionmentioning

confidence: 99%

Volume Tracking Simulation of Bubble Motion with Low Spatial Resolution

Hayashi

Sou

Tomiyama

2007

JFST

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The number of computational cells assigned to a small bubble is liable to be small in a volume tracking simulation of a poly-dispersed bubbly flow. The volume tracking method is, therefore, expected to at least give qualitatively reasonable predictions of bubble motion without assigning many cells. In this study, bubble motions in stagnant water and shear flows are simulated with low spatial resolutions using a volume tracking method proposed in our previous study. As a result, we confirm that (1) the method can yield correct characteristics of rising velocity and lateral motion of bubbles, and (2) the bubble volume and interface sharpness are kept well even after a bubble had experienced a large deformation in a strong shear flow.

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Investigation of Water-Vapor Two-Phase Flow Characteristics in a Tight-Lattice Core by Large-Scale Numerical Simulation, (I)

Cited by 12 publications

References 0 publications

Numerical Investigation of Cross Flow Phenomena in a Tight-Lattice Rod Bundle Using Advanced Interface Tracking Method

Numerical Investigation of Cross Flow Phenomena in a Tight-Lattice Rod Bundle Using Advanced Interface Tracking Method

Numerical simulation of two-phase flow behavior in Venturi scrubber by interface tracking method

Volume Tracking Simulation of Bubble Motion with Low Spatial Resolution

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