Published April 2005
| Version v1
Journal article
Mathematical adjoint equation of interface current method for neutron transport calculation
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
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 36111419
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ADJOINT DIFFERENCE METHOD; CURRENTS; EQUATIONS; INTERFACES; ITERATIVE METHODS; MULTIPLICATION FACTORS; NEUTRON SOURCES; NEUTRON TRANSPORT THEORY; T CODES
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; PARTICLE SOURCES; RADIATION SOURCES; TRANSPORT THEORY
Optional Information
- Notes
- 3 tabs., 7 refs.