Simplified thermal expansion modeling for liquid metal-cooled fast reactors
Creators
- 1. Department of Nuclear Engineering, North Carolina State University, Raleigh, NC (United States)
Description
While high resolution thermal expansion modeling in Liquid Metal-cooled Fast Reactors (LMFRs) is becoming more common, such models typically require supercomputers and hundreds of compute-hours. Practical reactor design calculations require simplified models and, therefore, more simplified thermal expansion modeling. In this paper, 3 thermal expansion models of varying complexity are compared using the computer program LUPINE: LMFR Utility for Physics Informed Nuclear Engineering. These 3 models are compared by modeling the Advanced Burner Reactor (ABR) benchmark with metallic fuel and a typical Lead-cooled Fast Reactor (LFR) with nitride fuel. It is observed that even the simplest thermal expansion model captures most of the reactivity effects of thermal expansion. The results demonstrate that all models perform acceptably and the sensitivity of keff to thermal expansion is largely determined by the reactor fuel type. Local power changes due to thermal expansion are also compared. It is determined that a model using spatially dependent thermal expansion in the axial direction is preferred as it incorporates the most geometric information and captures both reactivity and power distribution effects of thermal expansion. (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. 2248-2256
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
- 54119365
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; BURNERS; COMPUTER CODES; COMPUTERIZED SIMULATION; GEOMETRY; LEAD COOLED REACTORS; LMFBR TYPE REACTORS; NUCLEAR ENGINEERING; NUCLEAR FUELS; POWER DISTRIBUTION; REACTIVITY; REACTOR DESIGN; RESOLUTION; SUPERCOMPUTERS; THERMAL EXPANSION
- Descriptors DEC
- BREEDER REACTORS; COMPUTERS; DESIGN; DIGITAL COMPUTERS; ENERGY SOURCES; ENGINEERING; EPITHERMAL REACTORS; EXPANSION; FAST REACTORS; FBR TYPE REACTORS; FUELS; LIQUID METAL COOLED REACTORS; MATERIALS; MATHEMATICS; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTORS; SIMULATION
Optional Information
- Notes
- 10 refs.; Virtual meeting