(An) experimental investigation of the temperature behavior of a CANDU 37-element spent fuel bundle with air backfill공기중 CANDU 사용후 핵연료 다발의 온도 거동에 관한 실험적 연구

Cited 0 time in webofscience Cited 0 time in scopus
  • Hit : 481
  • Download : 0
As part of the thermal analysis of a CANDU spent fuel dry storage system, a series of experiment has been conducted using a thermal mock-up of a simulated CANDU spent fuel bundle in a dry storage basket. The experimental system was designed to obtain the maximum fuel rod temperature along with the radial and axial temperature distributions within the fuel bundle. The main purpose of these experiments was to characterize the relevant heat transfer mechanisms in a dry, vertically oriented CANDU spent fuel bundle, and to verify the MAXROT code developed for the thermal analysis of a CANDU spent fuel bundle in a dry storage basket. A total of 48 runs were made with 8 different power inputs to the 37-element heater rod bundle ranging from 5 to 40 W, while using 6 different band heaters power inputs from 0 to 250 W to maintain the basket wall at a desired boundary condition temperature at the steady state. The temperature distribution in a heater rod bundle was measured and recorded at the saturated condition for each set of heater rod power and band heaters power. To characterize the heat transfer mechanism involved, the experimental data were corrected analytically for radiation heat transfer and presented as a Nusselt number correlation in terms of the Rayleigh number of the heater rod bundle. The results show that the Nusselt number remains nearly constant and all the experimental dada fall within a conduction regime. The experimental data were compared with the predictions of the MAXROT code to examine the code``s accuracy and validity of assumptions used in the code. The MAXROT code explicitly models each representative fuel rod in a CANDU fuel bundle and couples the conductive and radiative heat transfer of the internal gas between rods. Comparisons between the measured and predicted maximum fuel rod temperatures of the simulated CANDU 37-element spent fuel bundle for all 48 tests show that the MAXROT code slightly over-predicts and the agreement is within 2.8...
Advisors
Chun, Moon-Hyun전문헌
Description
한국과학기술원 : 원자력공학과,
Publisher
한국과학기술원
Issue Date
1998
Identifier
143435/325007 / 000935123
Language
eng
Description

학위논문(박사) - 한국과학기술원 : 원자력공학과, 1998.8, [ x, 162 p. ]

Keywords

Heat transfer; CANDU; Spent fuel bundle; Experiment; 실험; 열전달; 중수로; 사용후핵연료다발

URI
http://hdl.handle.net/10203/48889
Link
http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=143435&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