Published Online: 2023-03-13
Published in Print: 2023-04-25
© 2023 Walter de Gruyter GmbH, Berlin/Boston
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Articles in the same Issue
- Frontmatter
- The 33rd German CFD Network of Competence Meeting: 20 years of advances in the numerical 3D simulation of reactor relevant flows
- Sustainable development of simulation setups and addons for OpenFOAM for nuclear reactor safety research
- Numerical investigations of flow in nuclear fuel assembly with spacer grid and OpenFOAM validation
- GRS contributions to flow-induced vibrations related activities in Europe
- Numerical simulation of subcooled flow boiling for nuclear engineering applications using OpenFOAM
- Model of terminal debris bed formation after a CANDU core collapse
- Weibull model for RUL estimation at RSG-GAS reactor implemented on PA01-AP01 secondary pump
- Study of the effect of virtual mass force on two-phase critical flow
- Using TRACE to establish the analysis model of Kuosheng nuclear power plant for decommissioning transition phase
- Post-LOCA control room dose analysis for Maanshan NPP using the AST methodology
- Lithium–lithium fusion evaporation research
- Study on the accidents analyses of a single channel for XADS by using MPC-LBE code
- Events
Articles in the same Issue
- Frontmatter
- The 33rd German CFD Network of Competence Meeting: 20 years of advances in the numerical 3D simulation of reactor relevant flows
- Sustainable development of simulation setups and addons for OpenFOAM for nuclear reactor safety research
- Numerical investigations of flow in nuclear fuel assembly with spacer grid and OpenFOAM validation
- GRS contributions to flow-induced vibrations related activities in Europe
- Numerical simulation of subcooled flow boiling for nuclear engineering applications using OpenFOAM
- Model of terminal debris bed formation after a CANDU core collapse
- Weibull model for RUL estimation at RSG-GAS reactor implemented on PA01-AP01 secondary pump
- Study of the effect of virtual mass force on two-phase critical flow
- Using TRACE to establish the analysis model of Kuosheng nuclear power plant for decommissioning transition phase
- Post-LOCA control room dose analysis for Maanshan NPP using the AST methodology
- Lithium–lithium fusion evaporation research
- Study on the accidents analyses of a single channel for XADS by using MPC-LBE code
- Events