IRAM combined with multi-group GMRES for solving Matrix MOC
Creators
- 1. Science Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu (China)
- 2. Department of Engineering Physics, Tsinghua University, Beijing (China)
Description
In the Matrix MOC, a linear algebraic equation system can be constructed by sweeping only once, and then solving the linear system takes the place of repeatedly characteristics sweeping. In neutron transport critical problems, keff is traditionally computed by power iteration (PI), whose convergence rate is deeply dependent on the dominance ratio. Large problems of practical interest often have dominance ratios close to 1, leading to slow convergence of PI. In this study, keff is computed by the Implicitly Restarted Arnoldi Method (IRAM) combined with multi-group GMRES, in which multi-group problems coupled by upscatter are solved directly, avoiding upscatter iteration. Numerical results of several benchmarks such as 2D C5G7 demonstrate that IRAM combined with multi-group GMRES can obtain good accuracy and higher efficiency compared with PI. (authors)
Additional details
Publishing Information
- Publisher
- China Nuclear Physics Society
- Imprint Place
- Beijing (China)
- ISBN
- 978-7-5022-6128-3
- Imprint Title
- Progress report on nuclear science and technology in China (Vol.3). Proceedings of academic annual meeting of China Nuclear Society in 2013, No.6--computational physics sub-volume
- Imprint Pagination
- 81 p.
- Journal Page Range
- p. 25-31
Conference
- Title
- 2013 academic annual meeting of China Nuclear Society
- Dates
- 10-14 Sep 2013
- Place
- Harbin (China)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 48068540
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; ALGORITHMS; COMPARATIVE EVALUATIONS; CONVERGENCE; EFFICIENCY; EQUATIONS; ITERATIVE METHODS; MATRICES; NEUTRON TRANSPORT
- Descriptors DEC
- CALCULATION METHODS; EVALUATION; MATHEMATICAL LOGIC; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT
Optional Information
- Notes
- 2 figs., 4 tabs., 13 refs.