Nuclear cross sectxons for fuel assemblies of the more recent Westinghouse designs, representing two different PWR reactor cores, are calculated as functions of average fuel temperature, moderator density, and moderator poison concentration. The cross-section functions are verified by referring to Westinghouse power-shape calculations and other analyses.
Computations on the side reflector resulted in significantly higher albedo values than used previously for BWR's in similar nodal codes. This led to an investigation of the influence of the internodal coupling coefficients on the power shape. It is concluded that the calculated power shape is strongly dependent, on the choice of coupling coefficients. However, it is shown that "the correct" set of coupling coefficients depends mostly on the nodal configuration, and that it is fairly independent of the power condition.
|Place of Publication||Roskilde, Denmark|
|Publisher||Risø National Laboratory|
|Number of pages||57|
|Publication status||Published - 1981|
- Computer calculations
- Coupling constants
- Cross sections
- Power distribution
- PWR type reactors