Thermal-Hydraulic Calculations for KUHFR with Reduced Enrichment Uranium Fuel

March 19, 1982
Kaichiro MIISHIMA and Toshikazu SHIBATA

Contents

1. INTRODUCTION  /p.8

2. CALCULATIONS  /p.10

2.1. Flow Distribution Calculation

2.2. Fuel plate Temperature Calculation

2.2.1. Coolant outlet temperature

2.2.2. Fuel plate temperature

2.3. Heat Transfer Coefficient

2.3.1. Heat transfer model

2.3.2. Single-phase heat transfer correlations

2.4. Burnout Heat Flux

2.4.1. Correlations

2.4.2. Experimental data

2.4.3. Comparisons of the correlations

2.5.Power Density Distribution

2.5.1. Radial power peaking factors

2.5.2. Axial power peaking factors

2.6. Engineering Hot Channel Factors

2.7. Thermal Pro_2erties of Fuel

3. RESULTS OF THE THERMAL-HYDRAULIC CALCULATIONS  /p.28

4. FLOW-INDUCED DEFORMATION OF FUEL PLATE  /p.37

5. CONCLUSIONS   /p.39

ACKNOWLEDGEMENT   /p.40

REFERENCES  /p.41

Appendix A. Computer code PLTEMP.  /p.43

Appendix B. Computer code PWRD.  /p.67

Appendix C. Power density distribution in the KUHFR.  /p.78

Appendix D. Comparison of the thermal-hydraulic analysis codes for the RERTR Program.  /p.91

Appendix E. Outline of the reactor •Core of the KUHFR  /p.101