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October 5, 2025Brazilian Journal of Radiation SciencesOpen Access

Development of a semi-analytical nodal methodology for one-dimensional eigenvalue problems based on multigroup neutron transport theory using the discrete ordinate formulation

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Authors

NPN. PinheiroFOFrancisco Bruno Souza OliveiraHFHermes Alves Filho

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Overview

This methodology demonstrates accuracy in eigenvalue problems for neutron transport theory, indicating efficient solutions.

Key Points

  • The method provides satisfactory eigenvalue solutions in neutron transport problems, ensuring accurate angular flux estimates.
  • Numerical results illustrate the method's effectiveness for typical benchmark problems in neutron transport theory.
  • The semi-analytical approach simplifies the computational process while maintaining solution accuracy across regions.
  • Iterative processes for estimating fission sources enhance continuity and reduce spatial truncation error in calculations.

Cite This Study

Pinheiro et al. (2025) studied this question.

synapsesocial.com/papers/68e24e6bd6d66a53c247391bhttps://doi.org/10.15392/2319-0612.2025.2940
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