Question: Problems: 6 - Based on the 0 . 0 2 5 - e V cross section and decay constants in Fig 2 - 1 6

Problems:
6- Based on the 0.025-eV cross section and decay constants in Fig 2-16(slides 14&15) and a thermal-neutron flux of 51013cm2-. Use the following cross section data.
\table[[Nuclide,capture,fission],[U-235,104b,586b
 Problems: 6- Based on the 0.025-eV cross section and decay constants

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