The upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles

被引:92
作者
Chen, S. K. [1 ]
Chen, Y. M. [1 ]
Todreas, N. E. [2 ]
机构
[1] Natl Tsing Hua Univ, Inst Nucl Engn & Sci, Hsinchu 30013, Taiwan
[2] MIT, Dept Nucl Sci & Engn, 77 Massachusetts Ave, Cambridge, MA 02139 USA
关键词
Wire-wrapped; Pressure drop; Friction factor; Correlation; EXISTING CORRELATIONS; FRICTION FACTORS; FAST-REACTOR; FLOW; SUBCHANNEL; ASSEMBLIES;
D O I
10.1016/j.nucengdes.2018.05.010
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The Cheng and Todreas (detailed) correlation (CTD) for wire-wrapped rod bundle friction factor published in 1986 has been identified in Chen a al. (2014) as the most used correlation for design and safety analyses for the Generation IV Sodium Fast Reactor(SFR). Since its publication in 1986, sixteen additional wire wrapped fuel bundle experiments have been performed worldwide providing data to supplement regions of minimal data in the bundle test data base. Based on this valuable new data, the CTD correlation has been refined in the following three aspects and renamed the Upgraded CTD (UCTD) Correlation. 1. The laminar to transition boundary Reynolds value has been significantly reduced. As well, a new laminar boundary equation is adopted which gives much lower value for the laminar boundary (Re bL ) as a function of P/D. 2. The transition region equation for bundle friction factor modified by Chen a al. (2013) to make the friction factor trajectory smoother moving through the turbulent boundary now has the exponent X reassessed to the value of 7. 3. The UCTD is now applicable to 7-pin bundle geometry. This has been achieved by adjusting the bundle average friction factor predicted by CTD for most bundle geometries such that the bundle fiction factor increases as the pin number increases. The cause of the previous inverse behavior was identified as the formulation of the wire drag and wire swirl empirical constants. A new process for finding these empirical constants is proposed and the constants set is calibrated by an 80 bundle data set. For Rehme's set of twenty 7 pin bundle experiments, the mean error prediction is now 9% which is about the measurement uncertainty and improved from 26% with CTD. The new correlation incorporating the above three improvements to the original CTD correlation is designated as the Upgraded CTD (UCTD) correlation. For the available 118 wire-wrapped bundles with pin number greater than 7 bundles, UCTD predicts the data in the transition and turbulent regimes with a mean error of 0.95% and a 90% confidence interval of +/- 14.8%, while both the CTD and the Rehme correlations (REH) have 1.5% higher values of this index. For the 27 available bundles with laminar data,(none of which are as small as 7 pin bundles) the performance of UCTD is slightly better than CTD with mean and RMS values of - 2.0%, and 9.5% versus - 3.0%, and 9.6%. (The REH correlation is not applicable to the laminar regime). A web-based numerical code of the UCTD correlation which incorporates these advances has been provided on the web for convenient design and research use.
引用
收藏
页码:356 / 373
页数:18
相关论文
共 38 条
[1]  
Baxi C.B., 1981, Heat Transfer and Fluid Flow in Nuclear Systems, P410
[2]   The thermal hydraulics in a rod bundle representative of the start-up core of the ALLEGRO Gas cooled Fast Reactor-Experimental and numerical approaches [J].
Berthoux, Marc ;
Cadiou, Thierry .
NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (10) :3372-3386
[3]   Review and proposal for best fit of wire-wrapped fuel bundle friction factor and pressure drop predictions using various existing correlations [J].
Bubelis, E. ;
Schikorr, M. .
NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (12) :3299-3320
[4]   Experimental study of the flow characteristics in an SFR type 61-pin rod bundle using iso-kinetic sampling method [J].
Chang, Seok-Kyu ;
Euh, Dong-Jin ;
Kim, Seok ;
Choi, Hae Seob ;
Kim, Hyungmo ;
Ko, Yung Joo ;
Choi, Sun Rock ;
Lee, Hyeong-Yeon .
ANNALS OF NUCLEAR ENERGY, 2017, 106 :160-169
[5]   Flow Distribution and Pressure Loss in Subchannels of a Wire-Wrapped 37-pin Rod Bundle for a Sodium-Cooled Fast Reactor [J].
Chang, Seok-Kyu ;
Euh, Dong-Jin ;
Choi, Hae Seob ;
Kim, Hyungmo ;
Choi, Sun Rock ;
Lee, Hyeong-Yeon .
NUCLEAR ENGINEERING AND TECHNOLOGY, 2016, 48 (02) :376-385
[6]   Evaluation of existing correlations for the prediction of pressure drop in wire-wrapped hexagonal array pin bundles [J].
Chen, S. K. ;
Todreas, N. E. ;
Nguyen, N. T. .
NUCLEAR ENGINEERING AND DESIGN, 2014, 267 :109-131
[7]   Numerical implementation of the Cheng and Todreas correlation for wire wrapped bundle friction factors-desirable improvements in the transition flow region [J].
Chen, S. K. ;
Petroski, R. ;
Todreas, N. E. .
NUCLEAR ENGINEERING AND DESIGN, 2013, 263 :406-410
[8]  
Cheng S., 1984, THESIS
[9]   HYDRODYNAMIC MODELS AND CORRELATIONS FOR BARE AND WIRE-WRAPPED HEXAGONAL ROD BUNDLES - BUNDLE FRICTION FACTORS, SUBCHANNEL FRICTION FACTORS AND MIXING PARAMETERS [J].
CHENG, SK ;
TODREAS, NE .
NUCLEAR ENGINEERING AND DESIGN, 1986, 92 (02) :227-251
[10]   Pressure drop modeling and comparisons with experiments for single- and two-phase sodium flow [J].
Chenu, A. ;
Mikityuk, K. ;
Chawla, R. .
NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (09) :3898-3909