Mass Flux and Enthalpy Distribution in a Rod Bundle for Single- and Two-Phase Flow Conditions

Lahey, R.T.; Shiralkar, B.S.; Radcliffe, D.W.

doi:10.1115/1.3449786

Cited by 44 publications

(4 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…In other words, the vapor or gas moves away from the smaller subchannels toward the larger subchannels. These phenomena were reported by many investigators, e.g., first by Lahey et al 2) and recently by Yadigaroglu et al 3) In general the observed behavior is called "void drift" phenomena. Conventional void drift models are based on the extension of the turbulence diffusion theory described in the textbook of Lahey and Moody.…”

Section: Flow Distribution In a Rod Bundle 1 Inter-subchannel Exmentioning

confidence: 68%

“…The hydrodynamic equilibrium flow in a rod bundle or inter-connected subchannel system would be characterized by the following conditions between adjacent subchannels: (1) no pressure differences, (2) no net mass or volume exchanges for each phase, and (3) no net momentum exchanges. It is noted that these conditions are on a time-averaged basis.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Prediction of the Equilibrium Two-Phase Flow Distributions in Inter-Connected Subchannel Systems.

Shirai

Ninokata

2001

J. Nucl. Sci. Technol.

View full text Add to dashboard Cite

This paper discusses the hydrodynamic equilibrium two-phase flow distribution phenomena in unheated subchannel systems. A set of two-fluid governing equations is solved and the solutions are compared with the equilibrium air-water two-phase flow experimental data from an interconnected two-subchannel test section in the slug to churn-turbulent flow regime. It is shown that the two-phase flow under the hydrodynamic equilibrium condition is distributed to make the minimum of possible pressure gradients. It is also shown that this minimum pressure gradient is closely related to the minimum energy dissipation of the total flow system. Finally a model is proposed to predict the hydrodynamic equilibrium two-phase flow distribution in a rod bundle as a minimization problem of the energy dissipation with mass continuity and momentum balance equations as the constraints.

show abstract

Section: Flow Distribution In a Rod Bundle 1 Inter-subchannel Exmentioning

confidence: 68%

Section: Introductionmentioning

confidence: 99%

Prediction of the Equilibrium Two-Phase Flow Distributions in Inter-Connected Subchannel Systems.

Shirai

Ninokata

2001

J. Nucl. Sci. Technol.

View full text Add to dashboard Cite

show abstract

“…Therefore, this code was verified for subcritical pressure and single phase flow conditions. 10) Analysis results and experimental data are compared in Fig. 4.…”

Section: Validation Of Analysis Codementioning

confidence: 99%

Subchannel Analysis to Investigate the Fuel Assembly for the Supercritical-water-cooled Power Reactor

Kitou

Nishida

Ishii

et al. 2004

J. Nucl. Sci. Technol.

View full text Add to dashboard Cite

The supercritical-water-cooled power reactor (SCPR) is expected to reduce power costs compared with those of current LWRs because of its high thermal efficiency and simple reactor system. The high thermal efficiency is obtained by supercritical pressure water cooling. The fuel cladding surface temperature increases locally due to a synergistic effect from the increased coolant temperature, the expanded flow deflection due to coolant density change and the decreased heat transfer coefficient, if the coolant flow distribution is non-uniform in the fuel assembly. Therefore, the SCPR fuel assembly is designed using a subchannel analysis code based on the SILFEED code for BWRs. The SCPR fuel assembly has many square-shaped water rods. The fuel rods are arranged around these water rods. The fuel rod pitch and diameter are 11.2 mm and 10.2 mm, respectively. Since coolant flow distribution in the fuel assembly strongly depends on the gap width between the fuel rod and the water rod, the proper gap width is examined. Subchannel analysis shows that the coolant flow distribution becomes uniform when the gap width is 1.0 mm. The maximum fuel cladding surface temperature is lower than 600 C and the temperature margin of the fuel cladding is increased in the design.

show abstract

“…The conservation equations (2)- (4) The 3×3 rod bundle test conducted by Lahey et al, 13) which was analyzed for the SILFEED code verification, 4) was applied as the first step of the verification of the present subchannel analysis method. They had performed 4 unheated single-phase flow test runs to measure mass flux distribution between subchannels and 13 heated two-phase flow test runs to measure mass flux and quality distributions.…”

Section: Subchannel Analysismentioning

confidence: 99%

Critical Power Analysis with Mechanistic Models for Nuclear Fuel Bundles, (I)

Naitoh¹,

Ikeda²,

Nishida

et al. 2002

Journal of Nuclear Science and Technology

View full text Add to dashboard Cite

The critical power analysis code for BWR fuel bundles, "CAPE-BWR", was developed. The objective of the development is to predict dryout phenomena of liquid film on fuel rod surfaces without tuning any parameters even for fuel bundle design improvements. The major features of the code are modular structure with mechanistic models and parallel computation. The calculation methods were divided into three steps: subchannel, liquid film flow and spacer effect analyses. The code was validated by the rod bundle test analyses. The overall comparison of calculated critical power with 166 measured data points showed −0.3% average difference with the standard deviation of 6.3%. The spatial domain decomposition method was applied for parallel computation of the spacer effect analysis. The parallelization efficiency was about 80%. The calculated dryout location agreed well with the measured one at the fullscale 8×8 bundle test. The code could trace the tendencies of the critical power depending on power distribution, spacer geometry and fluid conditions within a practical range of difference. From the calculation, difference of the critical power due to the spacer geometry was clarified to be caused by the difference of droplet deposition characteristics onto the liquid film.

show abstract

Mass Flux and Enthalpy Distribution in a Rod Bundle for Single- and Two-Phase Flow Conditions

Cited by 44 publications

References 0 publications

Prediction of the Equilibrium Two-Phase Flow Distributions in Inter-Connected Subchannel Systems.

Prediction of the Equilibrium Two-Phase Flow Distributions in Inter-Connected Subchannel Systems.

Subchannel Analysis to Investigate the Fuel Assembly for the Supercritical-water-cooled Power Reactor

Critical Power Analysis with Mechanistic Models for Nuclear Fuel Bundles, (I)

Contact Info

Product

Resources

About