KUR用燃料低濃縮度化のための熱水力解析
THERMAL-HYDRAULIC ANALYSIS FOR CORE CONVERSION TO THE USE OF LOW-ENRICHED URANIUM FUELS IN THE KUR

1984年12月7日　(December 7, 1984)
三島嘉一郎、神田啓治、柴田俊一
K. Mishima, K. Randa and T. Shibata

Contents

INTRODUCTION /p.1
CALCULATIONS /p.2
Flow Distribution Calculation /p.2
Fuel Plate Temperature Calculation /p.3
Coolant Outlet Temperature
Fuel Plate Temperature
Heat Transfer Coefficient /p.5
Heat Transfer Model
Single-Phase Heat Transfer Correlations
Critical Heat Flux /p.7
Heat Flux at Onset of Flow Instability /p.9
Thermal Conductivity of Fuel /p.10
Computer Code PLTEMP3 /p.11
Engineering Hot Channel Factors /p.11
Hot Channel Factor for Bulk Water Temperature Rise Fb
Hot Channel Factor for Heat Flux Fq
Hot Channel Factor for Heat Transfer Fh
Critical Velocity for Fuel Plate Deformation /p.18
CORE DESCRIPTION /p.19
Outline of the Current KUR Core /p. 19
Fuel Elements with LEU Fuels /p. 20
Core Model /p. 20
RESULTS AND DISCUSSIONS /p. 21
Results for the Current KUR /p. 21
Coolant Velocity and Flow Rate for LEU Fuels /p. 21
Flow Distribution in the Core /p. 22
Margin for Core Cooling /p. 23
Effects of. High Coolant Velocity /p. 24
Effect of Fuel Material on Peak Fuel Temperature /p. 24
SUMMARY /p. 25
ACKNOWLEDGEMENT /p. 26
REFERENCES /p. 27
APPENDIX A. COMPUTER CODE PLTEMP3 /p. 49