A novel form of uranium oxide (U3Og, density 8.5) is being considered for use as fuel for a research reactor. In this application, the uranium is enriched to 8.0 atom % 235U, and the remainder is 238U. The oxygen is pure 160. You may assume that. The atomic number of uranium is 92, and of oxygen is 8. The following table lists some of the relevant cross sections. Scattering, absorption and fission cross sections for thermal neutrons Isotopes, (b) sa (b) Sf (b) 235U0 99.3 587 23811 95 2 73 1.18x10

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A novel form of uranium oxide (U3O8 , density 8.5) is being considered for use
as fuel for a research reactor. In this application, the uranium is enriched to 8.0
atom % 235U, and the remainder is 238U. The oxygen is pure 160. You may
assume that . The atomic number of uranium is 92, and of oxygen is 8. The
following table lists some of the relevant cross sections.
Scattering, absorption and
fission cross sections for
thermal neutrons
Isotope ss (b) sa (b) St (b)
235U 0
99.3 587
1.18x10
238U
9.5 2.73
5
160
0.66 0.66 0
1. What is the weight fraction of 235U in the uranium?
2. What is the mean free path of thermal neutrons in this form of uranium
oxide?
3. How many fissions per second will occur in a small (1 cm³) uranium oxide
sample irradiated with a thermal neutron flux of 5 x 1015 cm²² s´1?
Transcribed Image Text:A novel form of uranium oxide (U3O8 , density 8.5) is being considered for use as fuel for a research reactor. In this application, the uranium is enriched to 8.0 atom % 235U, and the remainder is 238U. The oxygen is pure 160. You may assume that . The atomic number of uranium is 92, and of oxygen is 8. The following table lists some of the relevant cross sections. Scattering, absorption and fission cross sections for thermal neutrons Isotope ss (b) sa (b) St (b) 235U 0 99.3 587 1.18x10 238U 9.5 2.73 5 160 0.66 0.66 0 1. What is the weight fraction of 235U in the uranium? 2. What is the mean free path of thermal neutrons in this form of uranium oxide? 3. How many fissions per second will occur in a small (1 cm³) uranium oxide sample irradiated with a thermal neutron flux of 5 x 1015 cm²² s´1?
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