Solution of the One-Group Time-Dependent Neutron Transport Equation in an Infinite Medium by Polynomial Reconstruction
Author:
Affiliation:
1. University of Arizona, Department of Nuclear and Energy Engineering, Tucson, Arizona 85721
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE86-A18176
Reference5 articles.
1. The Collided Flux Expansion Method for Time-Dependent Neutron Transport
2. The Generation of Time-Dependent Neutron Transport Solutions in Infinite Media
3. Certain exact solutions of the nonstationary kinetic equation without taking retardation into account
4. Special Functions and Their Applications
5. Numerical evaluation of the slab albedo problem solution in one-speed anisotropic transport theory
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