The Suppression of Energy Discretization Errors in Multigroup Transport Calculations
Creators
- 1. Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Nuclear Engineering and Radiological Sciences
Description
The Objective of this project is to develop, implement, and test new deterministric methods to solve, as efficiently as possible, multigroup neutron transport problems having an extremely large number of groups. Our approach was to (i) use the standard CMFD method to 'coarsen' the space-angle grid, yielding a multigroup diffusion equation, and (ii) use a new multigrid-in-space-and-energy technique to efficiently solve the multigroup diffusion problem. The overall strategy of (i) how to coarsen the spatial an energy grids, and (ii) how to navigate through the various grids, has the goal of minimizing the overall computational effort. This approach yields not only the fine-grid solution, but also coarse-group flux-weighted cross sections that can be used for other related problems.
Files
47072957.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 15 p.
- Report number
- DOE/NEUP--09-839
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 47072957
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Descriptors DEI
- COORDINATES; CORRECTIONS; CROSS SECTIONS; ERRORS; MATHEMATICAL SOLUTIONS; MULTIGROUP THEORY; NEUTRON DIFFUSION EQUATION
- Descriptors DEC
- DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; EQUATIONS; NEUTRON TRANSPORT THEORY; PARTIAL DIFFERENTIAL EQUATIONS; TRANSPORT THEORY
Optional Information
- Contract/Grant/Project number
- AC07-05ID14517
- Funding organization
- USDOE National Nuclear Security Administration (NNSA). Nuclear Energy University Programs (NEUP) (United States)
- Secondary number(s)
- OSTIID--1087139