The 2006 CHF look-up table
DC Groeneveld, JQ Shan, AZ Vasić, LKH Leung… - … engineering and design, 2007 - Elsevier
CHF look-up tables are used widely for the prediction of the critical heat flux (CHF). The CHF
look-up table is basically a normalized data bank for a vertical 8mm water-cooled tube. The …
look-up table is basically a normalized data bank for a vertical 8mm water-cooled tube. The …
An overview of measurements, data compilations and prediction methods for the critical heat flux in water-cooled tubes
DC Groeneveld, A Ireland, J Kaizer, A Vasic - Nuclear Engineering and …, 2018 - Elsevier
This paper describes the history and state of the art of measuring and predicting the Critical
Heat Flux (CHF) in water-cooled tubes. Over the past 70 years, over 40,000 tube-CHF …
Heat Flux (CHF) in water-cooled tubes. Over the past 70 years, over 40,000 tube-CHF …
Diameter effect on critical heat flux
A Tanase, SC Cheng, DC Groeneveld… - Nuclear engineering and …, 2009 - Elsevier
The critical heat flux look-up table (CHF LUT) is widely used to predict CHF for various
applications, including design and safety analysis of nuclear reactors. Using the CHF LUT …
applications, including design and safety analysis of nuclear reactors. Using the CHF LUT …
DNBR limit analysis for the inner channel of annular fuel
J Guo, J Shan, B Yang, Y Peng, M Gui, S Ji - Annals of Nuclear Energy, 2024 - Elsevier
The departure from nucleate boiling ratios (DNBR) limit for annular fuel might vary from that
of conventional nuclear fuel rod assemblies due to the distinct features of annular fuel …
of conventional nuclear fuel rod assemblies due to the distinct features of annular fuel …
[PDF][PDF] METHODOLOGY OF CHF LOOK UP TABLE DERIVATION
JQ Shan, DC Groeneveld, AZ Vasić… - The 13 th …, 2005 - researchgate.net
The CHF look-up tables (LUT), because of its wide-range applicability, correct physical
trends, and relative accuracy, has been widely applied in nuclear reactor safety …
trends, and relative accuracy, has been widely applied in nuclear reactor safety …
Two-phase friction multiplier look-up table for water-steam flows in vertical tubes
B Öztüzün - acikbilim.yok.gov.tr
Two-phase steam-water flows are extensively used in many industrial facilities, especially in
nuclear power plants. The limits and capacity of these facilities are determined based on …
nuclear power plants. The limits and capacity of these facilities are determined based on …
Contribution à l'étude du flux de chaleur critique lors de l'ébullition eau vapeur dans les tubes évaporateurs
M Mebarkia - 2018 - dspace.univ-tebessa.dz
L'objectif essentiel de cette thèse est de présenter une vue d'ensemble sur l'ébullition de
l'eau à l'intérieur des tubes chauffants. Nous présentons brièvement le phénomène …
l'eau à l'intérieur des tubes chauffants. Nous présentons brièvement le phénomène …
[引用][C] Comparison analysis of chf parametric trends in vertical tube and 5x5 bundle
S Wang, J Shan, B Zhang, X Lang - 2015