(a) Assume that in each fission of 235U, 200 MeV is released. Assuming that5% of the energy is wasted in neutrinos, calculate the amount of 235 Uburned which would be necessary to supply at 30% efficiency, the wholeannual electricity consumption in Britain 50 × 10⁹ kWh(b) A thermal reactor contains 100 tons of natural uranium (density 19) andoperates at a power of 100 MW (heat). Assuming that the thermal cross-section of 235 U is 550 barns and that the uranium contains 0.7 % of 235 U.Calculate the neutron flux near the centre of the reactor by neglecting neu-tron losses from the outside, and assuming flux constant through out thelattice.[University of Liverpool 1959]

Dear Student, As you have posted two different questions but as per Q & A guidelines I will…

(a) Assume that in each fission of 235U, 200 MeV is released. Assuming that 5% of the energy is wasted in neutrinos, calculate the amount of 235 U burned which would be necessary to supply at 30% efficiency, the whole annual electricity consumption in Britain 50 × 10⁹ kWh

(a) Assume that in each fission of 235U, 200 MeV is released. Assuming that 5% of the energy is wasted in neutrinos, calculate the amount of 235 U burned which would be necessary to supply at 30% efficiency, the whole annual electricity consumption in Britain 50 × 10⁹ kWh

Elements Of Electromagnetics

7th Edition

ISBN:9780190698614

Author:Sadiku, Matthew N. O.

Publisher:Sadiku, Matthew N. O.

ChapterMA: Math Assessment

Section: Chapter Questions

Problem 1.1MA

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Question

(a) Assume that in each fission of 235U, 200 MeV is released. Assuming that
5% of the energy is wasted in neutrinos, calculate the amount of 235 U
burned which would be necessary to supply at 30% efficiency, the whole
annual electricity consumption in Britain 50 × 10⁹ kWh
(b) A thermal reactor contains 100 tons of natural uranium (density 19) and
operates at a power of 100 MW (heat). Assuming that the thermal cross-
section of 235 U is 550 barns and that the uranium contains 0.7 % of 235 U.
Calculate the neutron flux near the centre of the reactor by neglecting neu-
tron losses from the outside, and assuming flux constant through out the
lattice.
[University of Liverpool 1959]

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