Paper Title:
Construction of a High Temperature Grade 91 Sodium Component Test Loop
  Abstract

A large scale sodium test facility of ‘CPTL’(Component Performance Test Loop) for simulating thermal hydraulic behavior of the Korean demonstration fast reactor components such as IHX(Intermediate Heat Exchanger), DHX(Decay Heat Removal Heat Exchanger) and sodium pump under development by KAERI is to be constructed. The design temperature of this test loop is 600°C and design pressure is 1MPa. The three heat exchangers are made of Grade 91 steel. Another sodium test facility of the ‘STEF’(Sodium Thermal-Hydraulic Experimental Facility) will be constructed next to the CPTL facility to simulate the passive decay heat removal behavior in the sodium cooled fast reactor. In this paper, the overall facility features of the CPTL and STEF are introduced and preliminary conceptual design of the facilities are carried out.

  Info
Periodical
Materials Science Forum (Volumes 654-656)
Main Theme
Edited by
Jian-Feng Nie and Allan Morton
Pages
416-419
DOI
10.4028/www.scientific.net/MSF.654-656.416
Citation
H. Y. Lee, J. H. Lee, T. H. Lee, J. H. E. Lee, T. J. Kim, Y. B. Lee, "Construction of a High Temperature Grade 91 Sodium Component Test Loop", Materials Science Forum, Vols. 654-656, pp. 416-419, 2010
Online since
June 2010
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$32.00
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