TRANSV2 :A Thermal-.Hydraulic Analysis Code for Research Reactors

J. Klein and K. Mishima

Contents

1. INTRODUCTION  /p.1

2. HYDRAULIC ASPECT  /p.4

2.1. Method using pump characteristic curves

2.2. Analytical Method

2.3. Method using polynomials to approximate the characteristic curves

3. THERMAL ASPECT  /p.19

3.1. Energy balance in the fuel plate

3.2. Energy balance in the channel

4. THERMAL POWER GENERATION  /p.25

4.1. Control rods total withdrawn

4.2. Control rods fifty percent withdrawn

5. HEAT TRANSFER PACKAG  /p.29

5.1. Single-phase heat transfer correlations

5.2. Onset of nucleate boiling temperature

5.3. Critical heat flux

6. THERMAL PROPERTIES OF FUEL MATERIALS  /p.41

U-A1 alloy

UAlx -A1

U₃O₈-A1

U₃Si₂-A1

7. ENGINEERING HOT CHANNEL FACTORS  /p.46

Hot channel factor for bulk water temperature rise

Hot channel factor for heat flux

Hot channel factor for heat transfer

8. DESCRIPTION OF THE CODE  /p.50

9. INPUT DATA DESCRIPTION  /p.54

10. APPLICATION OF THE CODE TO THE CASE OF BLACKOUT IN THE JRR-3 AS A BENCHMARK PROBLEM  /p.62

ACKNOWLEDGEMENTS  /p.82

REFERENCES  /p.82

APPENDIX A. INPUT DATA FOR THE EXAMPLE  /p.85

APPENDIX B. OUTPUT OF THE EXAMPLE  /p.86 APPENDIX C. PROGRAM LIST OF TRANSV2  /p.106