Development of a subgrid model with a fine moving grid overlying a coarse Eulerian mesh for modeling reflood heat transfer

von Frepoli, Cesare
Veröffentlicht 2001

Digitilization and Management of Thermal Hydraulic Legacy Data Using FPoliDON Platform

von Frepoli, Cesare
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 6 of 9 (2020)

Design basis accident analysis methods for light water nuclear power plants

Veröffentlicht 2019

A Methodology to Satisfy Documentation Traceability and Transparency When Developing Evaluation Models for Safety Analysis Applications

von Frepoli, Cesare
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 11 of 14 (2018)

Investigation of Scaling Distortions for NRELAPS Model of NIST Facility Realized Using the Dynamical Systems Scaling Methodology

von Heagy, Stephen A.
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 9 of 9 (2020)

Development of Consistent Assessment Metrics and Modeling Guidelines for the Adequacy of System Codes in Modeliug Multidimensional Advection Diffusion Problems

von Frepoli, Cesare
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 10 of 14 (2018)

Assessment of COBRA-IE Code Capabilities in Modeling Fluid Mixing and Multidimensional Flow Using Data From the Vattenfall 1/5th Scale PWR Test Facility

von Mankosa, Michael G.
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 10 of 14 (2018)

Assessment of RELAPS-3D Code Capabilities in Modeling Fluid Mixing and Multidimensional Flow using Data from the International Standard Problem 43(ISP-43)

von Gosdin, Christopher A.
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 11 of 14 (2018)

Assessment of COBRA-IE Code Capabilities in Modeling Fluid Mixing and Multidimensional Flow using Data from the International Standard Problem 43(ISP-43)

von Gosdin, Christopher A.
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 14 of 14 (2018)