Question

Assume that only 235U-fissions. Calculate the macroscopic fission cross-section for the fuel given the following parameters.

Ignore the trace amounts of 234U in the fuel) Density of uranium dioxide wlo of 22 U in natural uranium MW of 235u Microscopic fission cross-section of 2 w/o of 23eU in natural uranium MW of 29U Microscopic fission cross-section of 28U MW of 1 C 10.5 g/cm 2.5 w/o (025) 235.0439 587 99.289 (99289) 238.0508 -0 15.9994

Answer 1