The Space–Time Neutron Kinetic Equations Obtained by the Semidirect Variational Method
Author:
Affiliation:
1. Knolls Atomic Power Laboratory, Schenectady, New York
2. Rensselaer Polytechnic Institute, Troy, New York
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE62-A26142
Reference11 articles.
1. The Application of Reactor Kinetics to the Analysis of Experiments
2. Effect of Delayed Neutrons on Nonlinear Reactor Stability
3. Boundedness and Stability in Nonlinear Reactor Dynamics
4. On the Range of Validity of Nonlinear Reactor Dynamics
5. Variational Representations in Reactor Physics Derived from a Physical Principle
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1. Solution of two-dimensional space–time multigroup reactor kinetics equations by generalized Padé and cut-product approximations;Annals of Nuclear Energy;2006-02
2. Time-dependent boundary source term for advanced nodal diffusion theory;Annals of Nuclear Energy;1999-08
3. A New Variational Functional for Space-Time Neutronics;Nuclear Science and Engineering;1997-01
4. Analytic solutions of the multigroup space-time reactor kinetics equations—I;Annals of Nuclear Energy;1986-01
5. Kinetics of Nuclear System Solution Methods for the Space-Time Dependent Neutron Diffusion Equation;Advances in Nuclear Science and Technology;1977
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