9.1 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 MW, electric power plant has a thermal power of approximately 3,000 MWh- a. What rate of fission reactions is required to produce this power? (Note: 1 eV = 1.6 x 10-¹9 J.) b. The reactor core consists of approximately 100 tonnes of UO, (1 tonne = 1,000 kg), which is enriched in 2U 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 235 U from occurring? C. Under the "U depletion scenario of part b, what mass of fission products and what mass of high-level wastes (HLW) would be produced?

Elements Of Electromagnetics
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Author:Sadiku, Matthew N. O.
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9.1
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
MW, electric power plant has a thermal power of approximately 3,000 MWh-
a.
What rate of fission reactions is required to produce this power? (Note: 1 eV = 1.6
x 10-¹9 J.)
b.
The reactor core consists of approximately 100 tonnes of UO₂ (1 tonne = 1,000
kg), which is enriched in 2U 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 25U from occurring?
C.
Under the 2U depletion scenario of part b, what mass of fission products and
what mass of high-level wastes (HLW) would be produced?
Transcribed Image Text:9.1 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 MW, electric power plant has a thermal power of approximately 3,000 MWh- a. What rate of fission reactions is required to produce this power? (Note: 1 eV = 1.6 x 10-¹9 J.) b. The reactor core consists of approximately 100 tonnes of UO₂ (1 tonne = 1,000 kg), which is enriched in 2U 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 25U from occurring? C. Under the 2U depletion scenario of part b, what mass of fission products and what mass of high-level wastes (HLW) would be produced?
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