Moderator circulation in CANDU reactors; An alternative approach for the tube matrix simulation
- Alexandria Univ. (Egypt). Faculty of Engineering
- Wisconsin Univ., Madison, WI (USA). Dept. of Nuclear Engineering and Physics
A two-dimensional computer code that is capable of predicting the moderator flow and temperature distribution inside CANDU calandria is presented. The code uses a new approach to simulate the calandria tube matrix by blocking the cells containing the tubes in the finite difference mesh. A jet momentum-dominant flow pattern is predicted in the nonisothermal case, and the effect of the buoyancy force, resulting from nuclear heating, is found to enhance the speed of circulation. Hot spots are located in low-velocity areas at the top of the calandria and below the inlet jet level between the fuel channels. A parametric study is carried out to investigate the effect of moderator inlet velocity,moderator inlet nozzle location, and geometric scaling. The results indicate that decreasing the moderator inlet velocity has no significant influence on the general features of the flow pattern (i.e., momentum dominant); however, too many high-temperature hot spots appear within the fuel channels.
- OSTI ID:
- 7176188
- Journal Information:
- Nuclear Technology; (USA), Journal Name: Nuclear Technology; (USA) Vol. 88:3; ISSN NUTYB; ISSN 0029-5450
- Country of Publication:
- United States
- Language:
- English
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CANDU TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
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FINITE DIFFERENCE METHOD
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TEMPERATURE DISTRIBUTION
THERMAL REACTORS
TWO-DIMENSIONAL CALCULATIONS