A calculation of the three-group flux distribution of the initial wet critical loading of KW reactor was made using the same calculation techniques as those employed in NPR three-group calculations. The calculation results are directly comparable to experimental data obtained during the KW loading. The calculated radial geometrical buckling of the critical loading is 48.2 {mu}b compared to a measured value of 49.8 {mu}b; these agree within estimated experimental error. The calculated reflector augmentation distance is 54.5 cm compared with a measured value of 49.2 cm. The three-group nuclear constants of the KW lattice components were calculated from 18-group data …
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Publisher Info:
General Electric Co., Richland, WA (United States). Hanford Atomic Products Operation
Place of Publication:
Richland, Washington
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A calculation of the three-group flux distribution of the initial wet critical loading of KW reactor was made using the same calculation techniques as those employed in NPR three-group calculations. The calculation results are directly comparable to experimental data obtained during the KW loading. The calculated radial geometrical buckling of the critical loading is 48.2 {mu}b compared to a measured value of 49.8 {mu}b; these agree within estimated experimental error. The calculated reflector augmentation distance is 54.5 cm compared with a measured value of 49.2 cm. The three-group nuclear constants of the KW lattice components were calculated from 18-group data (APEX-515) based on the flux spectrum of HW-63172. A cell calculation was made to determine the effective constants for the homogenized cell. The calculated k {infinity} of this cell came out 0.998 compared to a measured 1.034. Since the resonance capture of U-238 is difficult to treat, in three-group theory, all error was assumed to be in this parameter which was adjusted accordingly to give k {infinity} = 1.034. The resulting core parameters are given in Table I, along with parameters for the dry, unloaded core and the wet unloaded core.
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6 p.
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