Published 2011
| Version v1
Miscellaneous
Open
Nonlinear acceleration of transport criticality problems
Creators
- 1. Multiphysics Methods Group, Idaho National Laboratory, Idaho Falls, ID (United States)
- 2. Theoretical Division, Los Alamos National Laboratory, Los Alamos, NM (United States)
Description
We present a nonlinear acceleration algorithm for the transport criticality problem. The algorithm combines the well-known nonlinear diffusion acceleration (NDA) with a recently developed, Newton-based, nonlinear criticality acceleration (NCA) algorithm. The algorithm first employs the NDA to reduce the system to scalar flux, then the NCA is applied to the resulting drift-diffusion system. We apply a nonlinear elimination technique to eliminate the eigenvalue from the Jacobian matrix. Numerical results show that the algorithm reduces the CPU time a factor of 400 in a very diffusive system, and a factor of 5 in a non-diffusive system. (author)
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48022295.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 12 p.
- Report number
- INIS-BR--17053
Conference
- Title
- International conference on mathematics and computational methods applied to nuclear science and engineering
- Acronym
- M&C 2011
- Dates
- 8-12 May 2011
- Place
- Rio de Janeiro, RJ (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 48022295
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALGORITHMS; BENCHMARKS; BWR TYPE REACTORS; CRITICALITY; EIGENVALUES; EIGENVECTORS; FINITE DIFFERENCE METHOD; NEUTRON TRANSPORT; NONLINEAR PROBLEMS; SCALARS; TRANSPORT THEORY
- Descriptors DEC
- CALCULATION METHODS; ENRICHED URANIUM REACTORS; ITERATIVE METHODS; MATHEMATICAL LOGIC; MATHEMATICAL SOLUTIONS; NEUTRAL-PARTICLE TRANSPORT; NUMERICAL SOLUTION; POWER REACTORS; RADIATION TRANSPORT; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS