A thermal-neutron reactor is charged every year with enriched uranium containing 1.6 t of 235 U. When
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A thermal-neutron reactor is charged every year with enriched uranium containing 1.6 t of 235U. When the spent fuel is removed, it contains 400 kg of 235U and 560 kg of 239Pu. Assuming a conversion ratio CR = 0.6, what fraction of the reactor power was generated by fission of 239Pu? (Ignore radiative capture of thermal neutrons in both 235U and 239Pu, ignore production and fission of any other actinides, and assume that the energy releases in 235U and 239Pu fission are identical.)
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