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- W2483670457 abstract "This chapter discusses elliptic equations in nuclear reactor problems. Neutron diffusion equation is an elliptic equation that involves the determination of an eigenvalue. The diffusion equation arises as an approximation to the Boltzmann transport equation in the treatment of the neutron flux in a reactor in the steady state. To approximate the continuous range of neutron energies, the neutrons are divided into a number of energy groups. An elliptic eigenvalue problem is represented in finite differences by the problem of finding the eigenvalues of a matrix. Direct methods of solution can be used for the finite-difference equations; however, most reactor problems require very large numbers of mesh points, making iterative methods essential." @default.
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- W2483670457 date "1962-01-01" @default.
- W2483670457 modified "2023-09-26" @default.
- W2483670457 title "ELLIPTIC EQUATIONS IN NUCLEAR REACTOR PROBLEMS" @default.
- W2483670457 doi "https://doi.org/10.1016/b978-0-08-009660-5.50028-2" @default.
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