1986 AECL-UO Critical Heat Flux Lookup Table

Groeneveld, D.C.; Cheng, Siyuan; Doan, Thinh N.

doi:10.1080/01457638608939644

Cited by 258 publications

(32 citation statements)

References 3 publications

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“…Also, application of the K5 factors in this manner is not consistent with the intended usage in the published correlation. 4 Therefore, in the SEL High Power Flow Instability Test RELAP5-3D assessment, the K5 factors were applied as corrections to the local heat flux so that the heat flux value supplied to the CHF correlation is the "average heat flux from the start of boiling". This application of the K5 factors is consistent with the intended use as specified in the published correlation.…”

Section: Discussionmentioning

confidence: 99%

RELAP5-3D Code Validation for RBMK Phenomena

Fisher¹

1999

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The RELAP5-3D thermal-hydraulic code was assessed against Japanese Safety Experiment Loop (SEL) and Heat Transfer Loop (HTL) tests. These tests were chosen because the phenomena present are applicable to analyses of Russian RBMK reactor designs. The assessment cases included parallel channel flow fluctuation tests at reduced and normal water levels, a channel inlet pipe rupture test, and a high power, density wave oscillation test. The results showed that RELAP5-3D has the capability to adequately represent these RBMK-related phenomena. iv v SUMMARYThis report documents the assessment of the RELAP5-3D code against tests conducted in the Japanese Safety Experiment Loop (SEL) and Heat Transfer Loop (HTL). These tests provide data on selected phenomena that are relevant to RBMK safety analyses. The focus of the present work was in two areas. First, validation of the RELAP5-3D code was conducted using test data for which previous RELAP5/MOD3.2 assessment results are available. These assessment calculations were repeated with RELAP5-3D to determine whether the results were comparable to those previously obtained. Second, code validation calculations were conducted using RELAP5-3D for the SEL High Power Flow Instability Test, a case for which RELAP5/MOD3.2 failed to reproduce the response of the test facility.The assessment cases covered five phenomena identified as applicable to RBMK designs: The major conclusion was that RELAP5-3D has the capabilities to properly represent RBMK phenomena. The results showed that RELAP5-3D was capable of representing CCFL, break flow rates, manometer oscillations, flow pattern-induced oscillations, and other phenomena applicable to RBMK transient analyses. In most cases, the RELAP5-3D predictions were nearly identical to previous assessment results obtained using RELAP5/MOD3.2. The results also demonstrated that RELAP5-3D has the capability to predict the high power instability, or density wave oscillations, although it was necessary to adjust the channel pressure loss distribution to obtain this result. This adjustment was justified based on inconsistency and incompleteness of available data.The CHF model needs improvement; however, the successful prediction of the density wave oscillation response was not strongly dependent upon the precise prediction of dryout in the channel. Results of nodalization studies, which investigated multiple parallel paths in the high power channel, demonstrated that the fluid was well mixed and therefore a single-pipe (or single path) hydraulic model was adequate to represent the channel flow conditions. vi vii CONTENTS Abstract

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Section: Discussionmentioning

confidence: 99%

RELAP5-3D Code Validation for RBMK Phenomena

Fisher¹

1999

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“…Because of the complexity of the mechanism, few satisfactory analytical treatments are available, and the majority of the literature on this subject relies on experimental data for different geometries and fluid conditions. Bergles [6] has estimated that several hundred thousand data points have been obtained in such studies and over 200 correlations have been developed (e.g., Macbeth [7], Bowring [8], the Heat and Mass Transfer Section of the Scientific Council, USSR Academy of Sciences [9], Katto and Ohno [10], Groeneveld et al [11], Hall and Mudawar [12]). Applicability of these correlations to smaller diameter tubes (< ~1 mm) is problematical; likewise, most of the correlations were developed for flow boiling of water.…”

Section: Introductionmentioning

confidence: 99%

A review of the critical heat flux condition in mini-and microchannels

Roday

Jensen

2009

J Mech Sci Technol

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With ever increasing power dissipation in electronic chips that are shrinking in size, cooling demands are becoming more severe. Forced air cooling is reaching its operational limits, and single-phase liquid cooling in microchannels has been able to accommodate the rising heat fluxes. Further increases in computing (chip) power suggest that a switch from single-phase to boiling heat transfer will be needed. A major impediment to using boiling or forced convective vaporization for such a cooling application is the limiting critical heat flux (CHF) condition. In this paper, the CHF condition in microchannels is reviewed. Data from the literature are discussed, and new data for a range of operating and geometric conditions are presented. Influencing factors, parametric trends, phenomenological models, and other aspects of the CHF condition are discussed.

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“…Further extension of the lookup table can be achieved with multiplying the table CHF value by appropriate correction factors including subchannel or tube cross section factor 1 K , bundle factor 2 K , grid spacer factor 3 K , heated length factor 4 K , axial flux distribution factor 5 K , and flow factor 6 K [80][81]. With proper modifications, the lookup table can also be used for the prediction of CHFs of non-aqueous fluids [80,82].…”

Section: Predictive Models For Critical Heat Flux In the Literaturementioning

confidence: 99%

“…However, no pure theoretically-based predictive procedure is available [78] and most of the ad hoc equations are for the conditions of high pressure and high mass flux [79]. As an attempt of developing a predictive method for wide ranges of various parameters, Groeneveld, et al [80], based on a data bank of more than 15000 tube CHF data points, proposed a CHF lookup table for a vertical upward water flow in an 8-mm-diameter tube covering the parameter ranges of pressure 100-20000 kPa, mass flux 0-7500 kg/m2s, and vapor mass quality -50%-100%. Further extension of the lookup table can be achieved with multiplying the table CHF value by appropriate correction factors including subchannel or tube cross section factor 1 K , bundle factor 2 K , grid spacer factor 3 K , heated length factor 4 K , axial flux distribution factor 5 K , and flow factor 6 K [80][81].…”

Section: Predictive Models For Critical Heat Flux In the Literaturementioning

confidence: 99%