Published April 2005 | Version v1
Journal article

Mathematical adjoint equation of interface current method for neutron transport calculation

  • 1. Northwest Inst. of Nuclear Technology, Xi'an (China)

Description

This paper derives the mathematical adjoint equation of neutron transport equation, which is solved in hexagonal geometry by interface current method in the condition that the neutron source in cell adopts constant assumption. The calculation method of mathematical equation and the progress of inner and outer iteration are introduced. Based on the TPHEX code for forward equation calculation, the TPHEXJ0 code to calculate the mathematical equation is encoded. The calculation checkout proves that the keff of system calculated by TPHEXJ0 and TPHEX code are all in good agreement, and the calculation results of TPHEXJ0 code are reliable. (author)

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
26
Journal Issue
2
Journal Page Range
p. 97-101
ISSN
0258-0926

Optional Information

Notes
3 tabs., 7 refs.