2D/1D approximations to the 3D neutron transport equation. I: Theory
Creators
- 1. Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI 48109 (United States)
Description
A new class of '2D/1D' approximations is proposed for the 3D linear Boltzmann equation. These approximate equations preserve the exact transport physics in the radial directions x and y and diffusion physics in the axial direction z. Thus, the 2D/1D equations are more accurate approximations of the 3D Boltzmann equation than the conventional 3D diffusion equation. The 2D/1D equations can be systematically discretized, to yield accurate simulation methods for 3D reactor core problems. The resulting solutions will be more accurate than 3D diffusion solutions, and less expensive to generate than standard 3D transport solutions. In this paper, we (i) show that the simplest 2D/1D equation has certain desirable properties, (ii) systematically discretize this equation, and (iii) derive a stable iteration scheme for solving the discrete system of equations. In a companion paper [1], we give numerical results that confirm the theoretical predictions of accuracy and iterative stability. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 978-0-89448-700-2
- Imprint Title
- Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013
- Imprint Pagination
- 3016 p.
- Journal Page Range
- p. 1346-1357
Conference
- Title
- 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering
- Acronym
- M and C 2013
- Dates
- 5-9 May 2013
- Place
- Sun Valley, ID (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 45033759
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; APPROXIMATIONS; BOLTZMANN EQUATION; DIFFUSION EQUATIONS; FOURIER ANALYSIS; ITERATIVE METHODS; MATHEMATICAL SOLUTIONS; NEUTRON FLUX; NEUTRON TRANSPORT; NEUTRON TRANSPORT THEORY; ONE-DIMENSIONAL CALCULATIONS; REACTOR CORES; SIMULATION; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- CALCULATION METHODS; DIFFERENTIAL EQUATIONS; EQUATIONS; INTEGRO-DIFFERENTIAL EQUATIONS; KINETIC EQUATIONS; NEUTRAL-PARTICLE TRANSPORT; PARTIAL DIFFERENTIAL EQUATIONS; RADIATION FLUX; RADIATION TRANSPORT; REACTOR COMPONENTS; TRANSPORT THEORY
Optional Information
- Notes
- 16 refs.