Simulate annealing for group structure optimization
Creators
- 1. Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87545 (United States)
Description
It is challenging to select an appropriate group structure for multigroup neutron transport problem. Many group structures were chosen long ago, and the reasoning behind the creator's choices may be unknown. In this work, we apply the simulated annealing optimization method to develop improved group structures for a few test problems. Simulated annealing spans a large solution space before narrowing in on an optimal solution. Our solution space, however, is too large and too inconsistent for true optimization. Instead, we find potentially optimal group structures; ones that yield more accurate solutions than our standard group structures. We allow these group structures to be problem-dependent, with the view of developing a fast method to identify new group structures on-demand for different applications. The group structures used here outperform our current group structures of comparable size for the problems tested. The intent is for these optimized group structures to be used in a machine learning algorithm to help users choose a group structure based on problem characteristics, such as geometry and isotopics. (authors)
Availability note (English)
Available from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60526 (US)Additional details
Publishing Information
- Publisher
- ANS - American Nuclear Society
- Imprint Place
- La Grange Park (United States)
- Imprint Title
- Proceedings of the international conference on mathematics and computational methods applied to nuclear science and engineering - M and C 2021
- Imprint Pagination
- 2418 p.
- Journal Page Range
- p. 1453-1461
Conference
- Title
- International conference on mathematics and computational methods applied to nuclear science and engineering
- Acronym
- M and C 2021
- Dates
- 3-7 Oct 2021
- Place
- Raleigh, NC (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 54094385
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; GEOMETRY; MACHINE LEARNING; NEUTRON TRANSPORT; OPTIMIZATION
- Descriptors DEC
- ALGORITHMS; ARTIFICIAL INTELLIGENCE; LEARNING; MATHEMATICAL LOGIC; MATHEMATICS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; SIMULATION
Optional Information
- Notes
- 10 refs.; Virtual meeting