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The comparison of available data on PWR assembly thermal behavior with analytical predictions. Topical report (final)

J. Liu, +1 more
TLDR
In this paper, a comparison of available data with analytical predictions has been illustrated in this report, showing that COBRA can successfully predict the PWR normal operating conditions but cannot predict the trend under bulk quality conditions (X sub e > 0.02).
Abstract
The comparison of available data with analytical predictions has been illustrated in this report. Since few data on the cross flow are available, a study of parameters in the transverse momentum equation was performed to assess the sensitivity of results to their assumed values. It is confirmed that effects of these parameters on the overall results are not significant under PWR operating conditions. Data on subchannel properties of quality and mass flux were also assessed. From the data comparisons, it is evident that COBRA can successfully predict the PWR normal operating conditions but cannot predict the trend under bulk quality conditions (X sub e >0.02).

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Citations
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ReportDOI

The effect of virtual mass on the characteristics and the numerical stability in two-phase flow

TL;DR: In this article, a quantitative bound on the coefficient of the virtual mass terms was suggested for mathematical hyperbolicity and numerical stability, and it was concluded that the finite difference scheme with virtual mass model is restricted only by the convective stability conditions with the above suggested value.
Journal ArticleDOI

Thermal–hydraulic analysis of HPLWR fuel assembly cluster

TL;DR: In this article, a thermal hydraulic analysis of the high performance light water Reactor (HPLWR) fuel assembly cluster is presented, where the governing equations include energy, mass and momentum equations beside thermal hydraulic equations are solved numerically using the finite volume (upwind) method.
Journal ArticleDOI

Thermal-hydraulic analysis of a novel design super critical water reactor with Al2O3 nanofluid as a coolant

TL;DR: In this article, the thermal-hydraulic analysis of the SCWR reactor with a new geometric design is discussed, where the coolant and moderator circuits are separated and nanofluid has been used as coolant of the reactor core.

Transient thermal analysis of PWR’s by a single-pass procedure using a simplified nodal layout

TL;DR: In this article, the steady state one-stage simplified method was applied to the above two transient conditions and two transients (loss of coolant flow, seized rotor) were identified as candidates for analysis by this method.
References
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Journal ArticleDOI

Subchannel flow and enthalpy distributions at the exit of a typical nuclear fuel core geometry.

TL;DR: Simultaneous measurements of flow and enthalpy were made at the exits of two subchannels in a sixteen rod electrically heated full-scale model of a typical LWR fuel rod geometry.
ReportDOI

The effect of virtual mass on the characteristics and the numerical stability in two-phase flow

TL;DR: In this article, a quantitative bound on the coefficient of the virtual mass terms was suggested for mathematical hyperbolicity and numerical stability, and it was concluded that the finite difference scheme with virtual mass model is restricted only by the convective stability conditions with the above suggested value.
Journal ArticleDOI

Thermal–hydraulic analysis of HPLWR fuel assembly cluster

TL;DR: In this article, a thermal hydraulic analysis of the high performance light water Reactor (HPLWR) fuel assembly cluster is presented, where the governing equations include energy, mass and momentum equations beside thermal hydraulic equations are solved numerically using the finite volume (upwind) method.
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