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P02F10 Prediction of the Heat Transfer Deterioration for a Supercritical Pressure Water Flowing Vertically Upward in a Heated Tube

Cho, B. H. et al.

; Korean Nuclear Society; Yongpyong, South Korea, 2004; Oct, 0, 277-280 -- Korean Nuclear Society,; 2004 (pages 277-280)

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P02E06 Performance Verification Tests for the APR1400 Fluidic Device

Chu, I.-C. et al.

; Korean Nuclear Society; Yongpyong, South Korea, 2004; Oct, 0, 245-246 -- Korean Nuclear Society,; 2004 (pages 245-246)

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P04D09 Innovative Neutron Flux Mapping System and its Application to Kori#1 Unit

Cho, B.-H. et al.

; Korean Nuclear Society; Yongpyong, South Korea, 2004; Oct, 0, 631-632 -- Korean Nuclear Society,; 2004 (pages 631-632)

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Effect of Turbulent Prandtl Number on Simulation of Heat Transfer from supercritical Water in a Vertical Upward Tube Flow

Kim, S. H. et al.

; Korean Nuclear Society; Yongpyong, South Korea, 2004; Oct, 0, 205-206 -- Korean Nuclear Society,; 2004 (pages 205-206)

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  1. Kim, Y. I.  (2)
  2. Bae, Y. Y.  (2)
  3. Kim, S.-H.  (2)
  4. Park, J.‐Y.  (1)
  5. Chu, I. C.  (1)
  6. Chung, C. H.  (1)
  7. Choi, N.-H.  (1)
  8. Shin, C.-H.  (1)
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by this Author/Contributor:

  1. Cho, B. H.
  2. Kim, Y. I.
  3. Bae, Y. Y.
  4. Kim, S.-H.
  5. Park, J.‐Y.

on this subject:

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