The 1995 look-up table for critical heat flux in tubes

Groeneveld, D.C.; Leung, Lydie; Kirillov, P. L.; Bobkov, V. P.; Smogalev, I. P.; Vinogradov, V. N.; Huang, Xiaonuo; Royer, E.

doi:10.1016/0029-5493(95)01154-4

Cited by 286 publications

(84 citation statements)

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“…5. Within ranges of the reference CHF data, Groeneveld et al (1996)'s CHF table 15) showed the best pre- Fig. 4 Overall trends of CHF according to mass fluxes diction performance giving −10.5% for average error and 24.4% for RMS error.…”

Section: Resultsmentioning

confidence: 99%

The Effect of Vibration on Critical Heat Flux in a Vertical Round Tube

Lee

Chang

2003

Journal of Nuclear Science and Technology

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The CHF generally increases with vibration intensity, which is represented by vibrational Reynolds number (Re v ); the CHF enhancement is more dependent on amplitude than on frequency. CHF enhancement seems to come from the reinforced flow turbulent mixing effect by vibration in the vicinity of heat transfer surface. Based on the experimental results, an empirical correlation is proposed for the prediction of CHF enhancement by tube vibration. The correlation predicts the CHF enhancement ratio (En) with reasonable accuracy, with an average error rate of −2.18% and 27.75% for RMS.

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Section: Resultsmentioning

confidence: 99%

The Effect of Vibration on Critical Heat Flux in a Vertical Round Tube

Lee

Chang

2003

Journal of Nuclear Science and Technology

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“…The subchannel analysis for a 37S fuel bundle was performed to investigate the dryout power according to the increase of the creep rates of the pressure tube from 0% to 3.3% and 5.1% using the ASSERT code with a CHF lookup table [11]. For comparison of the dryout powers of the crept pressure tubes with those of the uncrept pressure tube, the dryout power ratio for a 37S fuel bundle, r DP,37S , was defined as follows: r DP ;37S ¼ Dryout Power crept PT;37S fuel bundle Dryout Power uncrept PT;37S fuel bundle :…”

Section: Pressure Tube Creep Effect On Dryout Power Of a 37s Fuel Bundlementioning

confidence: 99%

Thermalhydraulics of advanced 37-element fuel bundle in crept pressure tubes

Park

Song

2016

EPJ Nuclear Sci. Technol.

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Abstract. A CANDU-6 reactor, which has 380 fuel channels of a pressure tube type, is suffering from aging or creep of the pressure tubes. Most of the aging effects for the CANDU primary heat transport system were originated from the horizontal crept pressure tubes. As the operating years of a CANDU reactor proceed, a pressure tube experiences high neutron irradiation damage under high temperature and pressure. The crept pressure tube can deteriorate the Critical Heat Flux (CHF) of a fuel channel and finally worsen the reactor operating performance and thermal margin. Recently, the modification of the central subchannel area with increasing inner pitch length of a standard 37-element fuel bundle was proposed and studied in terms of the dryout power enhancement for the uncrept pressure tube since a standard 37-element fuel bundle has a relatively small flow area and high flow resistance at the central region. This study introduced a subchannel analysis for the crept pressure tubes loaded with the inner pitch length modification of a standard 37-element fuel bundle. In addition, the subchannel characteristics were investigated according to the flow area change of the center subchannels for the crept pressure tubes. Also, it was discussed how much the crept pressure tubes affected the thermalhydraulic characteristics of the fuel channel as well as the dryout power for the modification of a standard 37-element fuel bundle.

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“…Test sections with four (6,8,10, and 12 mm) diameters and variable lengths were used for the experiment at low pressure (P = 106~951 kPa) and low flow (G = 20~277 kg/m 2 s) conditions. Kim et al [5] studied flow boiling CHF in nanofluids.…”

Section: Introductionmentioning

confidence: 99%

“…The inner surfaces of the test section tube were observed using an FE-SEM and the zeta potentials of the Al2O3 nanofluids were measured before and after the CHF experiments. Most CHF experiments were conducted using Al2O3 nanofluids with low subcooling and were compared with the 1995 Groeneveld results in a look-up table [8].…”

Section: Introductionmentioning

confidence: 99%