Published April 2010 | Version v1
Journal article Metadata-only

Three dimension neutron transport characteristics method code. Pt.2: Numerical verification

Creators

  • 1. National Key Laboratory of Reactor System Design Technology, Nuclear Power Inst. of China, Chengdu (China)
  • 2. Department of Engineering Physics, Tsinghua Univ., Beijing (China)

Description

Three dimensional characteristics method code TCM is introduced and verified in this paper. And the influence of boundary interpolation, quadrature set and mesh size on accuracy of results are given. It is shown that TCM, using interpolation treatment of boundary condition, can calculate the neutron transport problems accurately, of which geometry and reflective boundary are arbitrary. (authors)

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
31
Journal Issue
2
Journal Page Range
p. 16-20
ISSN
0258-0926

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
42086748
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
Descriptors DEI
ACCURACY; BOUNDARY CONDITIONS; COMPUTER CALCULATIONS; EQUATIONS; GEOMETRY; INTERPOLATION; NEUTRON TRANSPORT; QUADRATURES; T CODES; THREE-DIMENSIONAL CALCULATIONS; VERIFICATION
Descriptors DEC
COMPUTER CODES; MATHEMATICAL SOLUTIONS; MATHEMATICS; NEUTRAL-PARTICLE TRANSPORT; NUMERICAL SOLUTION; RADIATION TRANSPORT

Optional Information

Notes
7 figs., 6 tabs., 6 refs.