Vibration effects on critical heat flux in a vertical round tube수직 원형관에서 진동이 임계 열유속에 미치는 영향에 관한 연구

Cited 0 time in webofscience Cited 0 time in scopus
  • Hit : 523
  • Download : 0
An experimental study has been performed to find out the relationship between CHF and vibration systematically. First, CHF experiment without vibration in vertical round tubes was conducted at low and medium pressure condition where the data are scarce. 251 CHF data in total have been collected to investigate the effect of independent parameters and to give information about the assessment of prediction method. It was revealed that the parametric CHF trends agreed well with those of previous studies. Within ranges of the given data, 1995 CHF table showed the best prediction performance giving -3.54% for average error and 18.1% for RMS error, and the backpropagation neural network (BPN) also gave reasonable prediction accuracy. Second, to find out the dynamic response of a tube at CHF condition, measurement of tube vibration in boiling process has been carried out under vertical upward flow at atmospheric condition. Vibration characteristics of the heated tube are significantly changed by heat transfer mode and flow patterns, therefore it is reasonable to say that the vibration measurement in heating condition can be an alternative method in the detection of heat transfer mode. In the case of liquid film dryout (LFD) type CHF condition, vibration could be regarded as negligible, however, these results cannot be extended to departure from nucleate boiling (DNB) type CHF mechanism Third, vibration controlled CHF tests are also accomplished to reveal the relationship between CHF and mechanical vibration. The CHF generally increases with vibration intensity that is represented by vibrational Reynolds number $(Re_v)$ and the CHF enhancement is more dependent on the amplitude than on the frequency. It seems that the CHF enhancement comes from reinforced fluid turbulence induced by vibration. Based on the heat transfer enhancement correlation, an empirical correlation for the prediction of CHF enhancement by tube vibration was suggested. The correlation predicts the CH...
Advisors
Chang, Soon-Heungresearcher장순흥researcher
Description
한국과학기술원 : 원자력및양자공학과,
Publisher
한국과학기술원
Issue Date
2003
Identifier
181061/325007 / 000985272
Language
eng
Description

학위논문(박사) - 한국과학기술원 : 원자력및양자공학과, 2003.2, [ xii, 146 p. ]

Keywords

convective heat transfer; nuclear fuel; flow induced vibration; critical heat flux; two phase flow; 이상유동; 대류 열전달; 핵연료; 유동기인진동; 임계 열유속

URI
http://hdl.handle.net/10203/48942
Link
http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=181061&flag=dissertation
Appears in Collection
NE-Theses_Ph.D.(박사논문)
Files in This Item
There are no files associated with this item.

qr_code

  • mendeley

    citeulike


rss_1.0 rss_2.0 atom_1.0