Improved multiphysics model of the High Temperature Engineering Test Reactor for the simulation of loss-of-forced-cooling experiments. (1st September 2023)
- Record Type:
- Journal Article
- Title:
- Improved multiphysics model of the High Temperature Engineering Test Reactor for the simulation of loss-of-forced-cooling experiments. (1st September 2023)
- Main Title:
- Improved multiphysics model of the High Temperature Engineering Test Reactor for the simulation of loss-of-forced-cooling experiments
- Authors:
- Labouré, Vincent
Ortensi, Javier
Martin, Nicolas
Balestra, Paolo
Gaston, Derek
Miao, Yinbin
Strydom, Gerhard - Abstract:
- Abstract: We present a multiphysics model of the High Temperature Engineering Test Reactor for comparison with past and predict future loss-of-forced-cooling (LOFC) experiments. The approach selected combines (1) 3-D full-core superhomogenization-corrected neutronics, (2) 3-D full-core homogenized or semi-heterogeneous heat transfer (macroscale), (3) 2-D axisymmetric fuel rod heat transfer (pin-scale), and (4) 1-D thermal-hydraulics channels. Although large uncertainties remain, the time and magnitude of the first power peak after re-criticality is predicted within 1.5 h and 175 kW, respectively. The novelty of our work includes (1) a new macroscale/pin-scale heat transfer coupling approach relying on gap conductance to drastically speed up numerical convergence by two orders of magnitude, (2) determination of a radial effective thermal conductivity, reproducing the semi-heterogeneous re-criticality time within one hour using a homogenized macroscale model, and (3) a preliminary study of the reactor's early behavior following a LOFC event, enabling further assessment of numerical models against fission power measurements. Highlights: A multiphysics model of the High Temperature Engineering Test Reactor is presented. The fission power overall behavior during a LOFC event is successfully reproduced. A novel heat transfer coupling approach is presented, with much faster convergence. A reasonable radial effective thermal conductivity is determined. The reactor's early behaviorAbstract: We present a multiphysics model of the High Temperature Engineering Test Reactor for comparison with past and predict future loss-of-forced-cooling (LOFC) experiments. The approach selected combines (1) 3-D full-core superhomogenization-corrected neutronics, (2) 3-D full-core homogenized or semi-heterogeneous heat transfer (macroscale), (3) 2-D axisymmetric fuel rod heat transfer (pin-scale), and (4) 1-D thermal-hydraulics channels. Although large uncertainties remain, the time and magnitude of the first power peak after re-criticality is predicted within 1.5 h and 175 kW, respectively. The novelty of our work includes (1) a new macroscale/pin-scale heat transfer coupling approach relying on gap conductance to drastically speed up numerical convergence by two orders of magnitude, (2) determination of a radial effective thermal conductivity, reproducing the semi-heterogeneous re-criticality time within one hour using a homogenized macroscale model, and (3) a preliminary study of the reactor's early behavior following a LOFC event, enabling further assessment of numerical models against fission power measurements. Highlights: A multiphysics model of the High Temperature Engineering Test Reactor is presented. The fission power overall behavior during a LOFC event is successfully reproduced. A novel heat transfer coupling approach is presented, with much faster convergence. A reasonable radial effective thermal conductivity is determined. The reactor's early behavior is investigated. … (more)
- Is Part Of:
- Annals of nuclear energy. Volume 189(2023)
- Journal:
- Annals of nuclear energy
- Issue:
- Volume 189(2023)
- Issue Display:
- Volume 189, Issue 2023 (2023)
- Year:
- 2023
- Volume:
- 189
- Issue:
- 2023
- Issue Sort Value:
- 2023-0189-2023-0000
- Page Start:
- Page End:
- Publication Date:
- 2023-09-01
- Subjects:
- Multiscale heat transfer coupling -- Effective thermal conductivity -- Reactor physics analysis -- High Temperature Engineering Test Reactor -- Loss-of-forced cooling
Nuclear energy -- Periodicals
Nuclear engineering -- Periodicals
621.4805 - Journal URLs:
- http://www.sciencedirect.com/science/journal/03064549 ↗
http://catalog.hathitrust.org/api/volumes/oclc/2243298.html ↗
http://www.elsevier.com/journals ↗ - DOI:
- 10.1016/j.anucene.2023.109838 ↗
- Languages:
- English
- ISSNs:
- 0306-4549
- Deposit Type:
- Legaldeposit
- View Content:
- Available online (eLD content is only available in our Reading Rooms) ↗
- Physical Locations:
- British Library DSC - 1043.150000
British Library DSC - BLDSS-3PM
British Library HMNTS - ELD Digital store - Ingest File:
- 27072.xml