Solution for a Nonlinear Nuclear Reactor with Negative Prompt Feedback and One-Group Delayed Neutron.

Abstract

The nonlinear space time neutron flux equation with negative prompt feedback and one-group delayed neutron is reduced by the use of a nonlinear transformation to a partial differential equation, in which the nonlinear term represents a small perturbation. The general procedure of solution for the resulting weakly nonlinear initial-boundary-value problem is then established by means of the method of successive approximation. Convergence of the analytical solution is also discussed. The solutions to a slab reactor core and a cylindrical reactor core are investigated here. Asymptotic stable equilibrium states are derived from each of these solutions. The present results are consistent with those obtained from previous stability analysis for the generalized buckling K greater or less than (Mu sub 0, sup 2), the lowest eigenvalue of the associated linear Helmholtz equation. (Author)

Document Details

Document Type
Technical Report
Publication Date
Jun 01, 1973
Accession Number
AD0764195

Entities

People

  • Nguyen Van Minh

Organizations

  • Naval Postgraduate School

Tags

DTIC Thesaurus Topics

  • Boundary Value Problems
  • Differential Equations
  • Eigenvalues
  • Equations
  • Feedback
  • Helmholtz Equations
  • Neutron Flux
  • Nuclear Reactors
  • Partial Differential Equations
  • Reactor Cores

Fields of Study

  • Mathematics
  • Physics

Readers

  • Control Systems Engineering.
  • Finite Element Method (FEM) for solving Partial Differential Equations (PDEs)
  • Solar Physics

Technology Areas

  • Space