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| Tiêu đề | Nuclear Reactor Physics |
|---|---|
| Tác giả | Weston M. Stacey |
| Trường học | Georgia Institute of Technology |
| Chuyên ngành | Nuclear Engineering |
| Thể loại | textbook |
| Năm xuất bản | Third, Revised Edition |
| Định dạng | |
|---|---|
| Số trang | 769 |
| Dung lượng | 31,38 MB |
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Ngày đăng: 30/05/2022, 09:42
Nguồn tham khảo
| Tài liệu tham khảo | Loại | Chi tiết | ||
|---|---|---|---|---|
| 1.35 – 10 MeV 9.1 keV – 1.35 MeV 0.4 eV – 9.1 keV 0.0 – 0.4 eVχ 0.575 0.425 0 0νΣ f (cm 1 ) 0.0096 0.0012 0.0177 0.1851Σ a (cm 1 ) 0.0049 0.0028 0.0305 0.1210Σ g g s 1 cm 1 0.0831 0.0585 0.0651 –D (cm) 2.162 1.087 0.632 0.354 | Sách, tạp chí |
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| 2 E. L. W ACHSPRESS , Iterative Solutions of Elliptic Systems and Applications to the Neutron Diffusion Equations of Reactor Physics, Prentice Hall, Englewood Cliffs, NJ (1973) | Khác | |||
| 6 R. H. H OWERTON et al., Evaluation Techniques and Documentation of Specific Evaluations of the LLL Evaluated Nuclear Data Library (ENDL), UCRL-50400, Vol. 15, Lawrence Livermore Laboratory, Livermore, CA (1970) | Khác | |||
| 4.1 Solve the neutron balance equation in the slowing-down range for the neutron flux, and determine the neutron slowing-down density, for a mixture of nonhydrogenic moderators and no absorption. Compare the result with Eq. (4.20) in the no-absorption limit | Khác | |||
| 4.2 Consider a very large block of material with composition ( 235 U = 0.002 × 10 24 at / cm , 3 238 U = 0.040 × 10 24 at / cm 3 , H 2 O = 0.022 × 10 24 at / cm , 3 Fe = 0.009 × 10 24 at / cm 3 ) and temperature T = 400 ° C. Calculate and plot the neutron fl ux energy distribution in the fi ssion, slowing-down, and thermal regions | Khác | |||
| 4.3 Carry out the steps to demonstrate that the Maxwellian distribution of Eq. (4.29) satisfies the equilibrium neutron balance equation of Eq. (4.27) | Khác | |||
| 4.4 Calculate the thermal group absorption cross section for 235 U at T n = 300, 400, and 500 °C | Khác | |||
| 4.5 Calculate the infinite multiplication constant and the relative group fluxes in a very large fuel assembly with the four-group constants given in Table P4.5 | Khác | |||
| 4.6 The radiative capture cross section for a certain isotope is measured at the following energies: 50 eV, 200 barns; 100 eV, 245 barns; 150 eV, 275 barns;300 eV, 200 barns; 350 eV, 180 barns; 400 eV, 210 barns. Calculate a multigroup capture cross section for the group E g = 75 eV, E g 1 = 425 eV | Khác | |||
| 4.7 Calculate the resonance escape probability for the 6.67 eV 238 U resonance at T = 300 ° C when the moderator scattering cross section per | Khác |
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