A variational nodal approach to 2D/1D pin resolved neutron transport for pressurized water reactors

Tengfei Zhang, E. E. Lewis, M. A. Smith, W. S. Yang, Hongchuna Wu

Research output: Contribution to journalArticlepeer-review

34 Scopus citations


A two-dimensional/one-dimensional (2D/1D) variational nodal approach is presented for pressurized water reactor core calculations without fuel-moderator homogenization. A 2D/1D approximation to the within-group neutron transport equation is derived and converted to an even-parity form. The corresponding nodal functional is presented and discretized to obtain response matrix equations. Within the nodes, finite elements in the x-y plane and orthogonal functions in z are used to approximate the spatial flux distribution. On the radial interfaces, orthogonal polynomials are employed; on the axial interfaces, piecewise constants corresponding to the finite elements eliminate the interface homogenization that has been a challenge for method of characteristics (MOC)-based 2D/1D approximations. The angular discretization utilizes an evenparity integral method within the nodes, and low-order spherical harmonics (PN) on the axial interfaces. The x-y surfaces are treated with high-order PN combined with quasi-reflected interface conditions. The method is applied to the C5G7 benchmark problems and compared to Monte Carlo reference calculations.

Original languageEnglish (US)
Pages (from-to)120-133
Number of pages14
JournalNuclear Science and Engineering
Issue number2
StatePublished - May 2017


  • 2D/1D variational nodal method
  • Eliminating the interface homogenization

ASJC Scopus subject areas

  • Nuclear Energy and Engineering


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