| Title: |
Tool developments in the OpenMC code: Correlated Sampling and Transient Fission Matrix approach using OpenFOAM CFD mesh |
| Authors: |
Laureau, Axel; Merle, E |
| Contributors: |
Laboratoire de Physique Subatomique et de Cosmologie (LPSC); Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS)-Université Grenoble Alpes (UGA)-Institut polytechnique de Grenoble - Grenoble Institute of Technology (Grenoble INP); Université Grenoble Alpes (UGA); Laboratoire de physique subatomique et des technologies associées (SUBATECH); Institut National de Physique Nucléaire et de Physique des Particules du CNRS (IN2P3)-Centre National de la Recherche Scientifique (CNRS)-IMT Atlantique (IMT Atlantique); Institut Mines-Télécom Paris (IMT)-Institut Mines-Télécom Paris (IMT)-Nantes université - UFR des Sciences et des Techniques (Nantes univ - UFR ST); Nantes Université - pôle Sciences et technologie; Nantes Université (Nantes Univ)-Nantes Université (Nantes Univ)-Nantes Université - pôle Sciences et technologie; Nantes Université (Nantes Univ)-Nantes Université (Nantes Univ) |
| Source: |
M&C 2023: The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering ; https://hal.science/hal-04298512 ; M&C 2023: The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Aug 2023, Niagara Falls, Canada |
| Publisher Information: |
CCSD |
| Publication Year: |
2023 |
| Collection: |
Université de Nantes: HAL-UNIV-NANTES |
| Subject Terms: |
OpenMC; Correlated Sampling; Nuclear Data uncertainty; TFM; Thermohydraulics; [PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex]; [PHYS.NUCL]Physics [physics]/Nuclear Theory [nucl-th] |
| Subject Geographic: |
Niagara Falls |
| Time: |
Niagara Falls, Canada |
| Description: |
International audience ; This article presents the developments performed to enlarge the application of the OpenMC neutron transport code for thermohydraulics coupling and nuclear data uncertainty propagation. These developments rely firstly on the addition of the Correlated Sampling (CS) technique, which allows to propagate the impact of thermal feedback or cross section sampling on the neutronic calculations thanks to neutron weight modifications. The Correlated Sampling technique is associated here to Computer Aided Design (CAD) based mesh and to the Transient Fission Matrix (TFM) approach. These three elements are used together to allow a global handling of the neutronics-thermohydraulics coupling: the TFM approach deals with the neutron kinetics using a pre-calculation of the neutron transport stored in matrices, the Correlated Sampling technique provides the impact of the thermal feedbacks on the matrices, and the CAD mesh is used to define the volumes associated to each bin of the matrices in order to get the results on the same format as the Computational Fluid Dynamics (CFD) code to be coupled to neutronics, here the OpenFOAM code. Both the implementations and the verifications done are detailed in the article, together with a discussion on the current limitations. |
| Document Type: |
conference object |
| Language: |
English |
| Relation: |
https://hal.science/hal-04631846v1 |
| Availability: |
https://hal.science/hal-04298512; https://hal.science/hal-04298512v1/document; https://hal.science/hal-04298512v1/file/mc2023_alaureau_full.pdf |
| Rights: |
https://about.hal.science/hal-authorisation-v1/ ; info:eu-repo/semantics/OpenAccess |
| Accession Number: |
edsbas.646A4F1B |
| Database: |
BASE |