Lookup Tables for Predicting CHF and Film-Boiling Heat Transfer: Past, Present, and Future

Groeneveld, D.C.; Leung, Lydie; Guo, Yuting; Vasić, A.Ž; Nakla, Meamer El; Peng, Shinian; Yang, Jun; Cheng, Siyuan

doi:10.13182/nt152-87

Cited by 31 publications

(16 citation statements)

References 21 publications

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“…Other effects such as from the use of bundles (K2), grids (K3), heated length variation (K4), axial flux distribution factor (K5), radial or circumferential flux distribution factor (K6), floworientation factor (K7), and vertical low-flow factor (K8), have been developed [30] for use with the CHF tables. Only K1 is accounted for in V4.…”

Section: List Of Tablesmentioning

confidence: 99%

A User’s Guide to the PLTEMP/ANL Code (V.4.3)

Kalimullah

Olson

Feldman

2021

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Section: List Of Tablesmentioning

confidence: 99%

A User’s Guide to the PLTEMP/ANL Code (V.4.3)

Kalimullah

Olson

Feldman

2021

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“…The equations used for K 3 by Groeneveld, et al 21 , Groeneveld, et al 16 , and Groeneveld, et al 23 are:…”

Section: K 3 Chf Factor (Grid Spacers)mentioning

confidence: 99%

“…In Groeneveld, et al 21 L sp is not defined. In Groeneveld, et al 16 L sp is the distance from the upstream spacer plane.…”

Section: K 3 Chf Factor (Grid Spacers)mentioning

confidence: 99%

Evaluation of a uranium zirconium hydride fuel rod option for conversion of the MIT research reactor (MITR) from highly-enriched uranium to low-enriched uranium

Dunn

Wilson

Feldman

et al. 2017

Nuclear Engineering and Design

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The conversion of the Massachusetts Institute of Technology Reactor (MITR) from the use of highly-enriched uranium (HEU) fuel-plate assemblies to low-enriched uranium (LEU) by replacing the HEU fuel plates with specially designed General Atomics (GA) uranium zirconium hydride (UZrH) LEU fuel rods is evaluated. The margin to critical heat flux (CHF) in the core, which is cooled by light water at low pressure, is evaluated analytically for steady-state operation. A form of the Groeneveld CHF lookup table method is used and described in detail. A CHF ratio of 1.41 was found in the present analysis at 10 MW with engineering hot channel factors included. Thus, the nominal reactor core power, and neutron flux performance, would need to be reduced by at least 25% in order to meet the regulatory requirement of a minimum CHF ratio of 2.0.

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“…(10) until the predicted CHF becomes the same as the supplied heat flux. The CHF is calculated using the CHF look-up table [14] along with the CHF correction factors for diameter and heated length [13]. This method predicts the CHF location with an average error of 1.9% and an RMS error of 13.1%.…”

Section: 2mentioning

confidence: 99%

“…The fully developed heat transfer coefficient h FD is determined from the film-boiling look-up table [4] by applying the local flow conditions at the corresponding location of interest. Empirical correction factors regarding the heated length and diameter in Groeneveld et al [13] were used for the application of the CHF look-up table [14] and film-boiling look-up table [4]. However, the predictions of the CHF and heat transfer coefficients were not arbitrarily adjusted to eliminate any systematic biases as in the conventional correlations [6,9].…”

mentioning

confidence: 99%

An improved heat transfer correlation for developing post-dryout region in vertical tubes

Nguyen

Moon

2015

Nuclear Engineering and Technology

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a b s t r a c tA developing post-dryout region is characterized by significant heat transfer enhancements compared with the fully developed post-dryout region. The heat transfer enhancements are mainly due to upstream disturbance and entrained droplets in the region immediately downstream of the critical heat flux location. In this paper, an improved heat transfer correlation is developed for the developing post-dryout regions in vertical tubes over a wide range of flow conditions. The correlation represents a correction factor for the fully developed film-boiling look-up table to be applied to the developing post-dryout region. The new correlation significantly improves the heat transfer prediction in the developing post-dryout regions and provides very good agreement with the experimental data.

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Lookup Tables for Predicting CHF and Film-Boiling Heat Transfer: Past, Present, and Future

Cited by 31 publications

References 21 publications

A User’s Guide to the PLTEMP/ANL Code (V.4.3)

A User’s Guide to the PLTEMP/ANL Code (V.4.3)

Evaluation of a uranium zirconium hydride fuel rod option for conversion of the MIT research reactor (MITR) from highly-enriched uranium to low-enriched uranium

An improved heat transfer correlation for developing post-dryout region in vertical tubes

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