Simulation of TREAT cores using high-fidelity neutronics code PROTEUS
Creators
- 1. Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL, 60439 (United States)
Description
Two TREAT experimental cores, Minimum Critical Core (MinCC) and M8CAL, were simulated for verification and validation tests of PROTEUS. Due to the significant neutron streaming effect in the test problems via air cooling channels and hodoscope slot, the MOCEX solver of PROTEUS was used for the simulation. For systematic verification tests, 2D and 3D single fuel element, partial core, and whole-core problems were constructed and simulated, aiming at 3D whole-core calculations with explicit geometry configurations. Meshes were generated using the PROTEUS mesh toolkit combined with CUBIT. Multigroup cross sections were generated from the Serpent Monte Carlo code based on the 11 energy group structure to focus on the verification of the transport solution accuracy of PROTEUS. The simulation results for various cases based on MinCC and M8CAL indicated that the PROTEUS eigenvalues and power distributions were in very good agreement with Serpent solutions. (authors)
Additional details
Publishing Information
- Publisher
- Korean Nuclear Society - KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Pagination
- 6 p.
Conference
- Title
- International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering 2017
- Acronym
- M and C 2017
- Dates
- 16-20 Apr 2017
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- France
- INIS RN
- 53074287
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CROSS SECTIONS; EIGENVALUES; FUEL ELEMENTS; GEOMETRY; HODOSCOPES; MONTE CARLO METHOD; NEUTRON TRANSPORT; NUCLEAR FUELS; POWER DISTRIBUTION; THREE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL CALCULATIONS; VALIDATION; VERIFICATION
- Descriptors DEC
- CALCULATION METHODS; ENERGY SOURCES; FUELS; MATERIALS; MATHEMATICS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; REACTOR COMPONENTS; REACTOR MATERIALS; SIMULATION; TESTING
Optional Information
- Notes
- 11 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses