We want to get an idea of the actual mass of 235U involved in powering a nuclear power plant. Assume that a single fission event releases 200 MeV of thermal energy. A 1,000 MWe electric power plant has a thermal power of approximately 3,000 MWth.

What rate of fission reactions is required to produce this power? (Note: 1 eV = 1.6

1019 J.)

The reactor core consists of approximately 100 tonnes of UO2 (1 tonne = 1,000

kg), which is enriched in 235U to 4%. How many full-power years could the reactor operate if all of the 235U were to be fissioned? What factors prevent such complete depletion of the 235U from occurring?

Under the 235U depletion scenario of part b, what mass of fission products and what mass of high-level wastes (HLW) would be produced?