TEMPERATURE STRUCTURE IN THE GAS COOLED REACTOR FUEL ELEMENTS USING A SCALLOPED COOLANT CHANNEL
An analysis of the temperature structure in the GCR2 fuel elements and coolant stream at the position where the maximum fuel element surface temperature exists was presented in a previous paper (CF-58-5-97). It was felt that the peripheral temperature variation existing on the fuel rods as brought out in that analysis was due mainly to the poor flow distribution of the coolant with respect to the heat flux. The most expedient way to alleviate this situation without changing the fuel element assembly itself is to scallop the channel so that it becomes, in effect, seven channels merged together to form a single passage. This geometry was studied by use of the IBM 704 digital computer in much the same way the earlier problems were investigated. Since the heat transfer coefficient depends much more strongly on free flow area than on equivalent diameter, the free flow area of the model reported on was made equal to that of the 3.25 in. circular channel so that a comparison of the results of the two configurations would be meaningful.(auth)
- Research Organization:
- Oak Ridge National Lab., Tenn.
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-13-011487
- OSTI ID:
- 4277286
- Report Number(s):
- CF-59-3-39
- Country of Publication:
- United States
- Language:
- English
Similar Records
CAT--AN IBM 704 PROGRAM FOR COOLANT ACTUATED TRANSIENTS IN AN OPEN-LATTICE CORE
TEMPERATURE STRUCTURE IN GAS COOLED REACTOR FUEL ELEMENTS AND COOLANT CHANNEL
PATHFINDER ATOMIC POWER PLANT SUPERHEATER TEMPERATURE EVALUATION ROUTINE. AN IBM-704 COMPUTER PROGRAM
Technical Report
·
Sun Jan 31 23:00:00 EST 1960
·
OSTI ID:4182132
TEMPERATURE STRUCTURE IN GAS COOLED REACTOR FUEL ELEMENTS AND COOLANT CHANNEL
Technical Report
·
Tue May 27 00:00:00 EDT 1958
·
OSTI ID:4316685
PATHFINDER ATOMIC POWER PLANT SUPERHEATER TEMPERATURE EVALUATION ROUTINE. AN IBM-704 COMPUTER PROGRAM
Technical Report
·
Mon Oct 30 23:00:00 EST 1961
·
OSTI ID:4818504