Fast power reactor simulation employing a GPU-based continuous-energy Monte Carlo method
Creators
- 1. Department of Nuclear Engineering, Seoul National University, Building 32, 1 Gwanak-ro, Gwanak-gu, Seoul, 008826 (Korea, Republic of)
Description
The computational barrier imposed on the continuous-energy Monte Carlo (MC) power reactor calculation was overcome by exploiting state-of-the-art GPU computing techniques. PRAGMA is a GPU-based continuous-energy MC code tailored to commercial PWR analysis, and it can exploit gaming GPUs to retain practicality. The unionized grid method is improved for GPUs by introducing a linear hashing scheme, and the random neutrons are cast into GPUs by an event-based tracking algorithm. Fuel partitioning and energy sort schemes render significant performance for depleted fuel analysis. Dedicated calculation schemes for power reactors such as multilevel spectral collapse (MSC) for depletion, localized delta-tracking (LDT), domain decomposition, and fission source convergence acceleration with CMFD and ramp-up enable efficient large-scale power reactor simulations employing massive particles. The performance of PRAGMA using a single gaming GPU was equivalent to that of a conventional MC code using 500 cores of a flagship CPU, and the full-scale BEAVRS cycle 1 depletion calculation using 360 billion histories was completed in 16 hours employing 24 gaming GPUs
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. 182-192
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
- 54081682
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALGORITHMS; COMPUTERIZED SIMULATION; CONVERGENCE; FISSION; MONTE CARLO METHOD; NEUTRONS; NUCLEAR FUELS; PERFORMANCE; PWR TYPE REACTORS; RANDOMNESS
- Descriptors DEC
- BARYONS; CALCULATION METHODS; ELEMENTARY PARTICLES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FERMIONS; FUELS; HADRONS; MATERIALS; MATHEMATICAL LOGIC; NUCLEAR REACTIONS; NUCLEONS; POWER REACTORS; REACTOR MATERIALS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 19 refs.; Virtual meeting