Assembling the Second Generation Multiphase-CFD Closures, One Bubble at a Time

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

A Parametric CFD Boiling Study Using State-of-the-Art Two-Phase and Boiling Closure Models

von Yoo, Junsoo
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 4 of 9 (2020)

Assessment of MIT Momentum Closure Relations to Developing, Bubbly Flow Regimes

von Casel, Brian
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 1 of 9 (2020)

Addressing the Usage of CFD Within the CSAU Framkework for Nuclear Reactor Safety Analysis Simulations

von Acton, Michael
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 7 of 9 (2020)

Development and Multi-Level Validation of a Mechanistic Heat Flux Partitioning Model for Boiling Heat Transfer

von Kommajosyula, Ravikishore
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 3 of 9 (2020)

ICONE2020-16080 Toward Industrial Applicability of DNB Predictions in CFD With Improved Wall Boiling Models

von Feng, Jinyong
Veröffentlicht in ASME International Conference on Nuclear Engineering (2020 : Online) Proceedings of the ASME International Conference on Nuclear Engineering - 2020 ; Volume 1: Beyond design basis, codes and standards, computational fluid dynamics (CFD), decontamination and decommissioning, nuclear fuel and engineering, nuclear plant engineering (2020)

Assessment of Multiphase CFD with Zero Closure Models for Boiling Water Reactor Fuel Assemblies

von Yoon, Su-Jong
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 6 of 14 (2018)

Evaluation of Turbulence Modeling Approaches for the Prediction of Cross-Flow in a Helical Tube Bundle

von Feng, Jinyong
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 1 of 9 (2020)

Progress Toward Simulating Departure from Nucleate Boiling (DNB) at High Pressure Applications with Selected Wall Boiling Closures

von Kim, Seung Jun
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 5 of 9 (2020)

A Criterion to Classify Void Fraction Profiles in Adiabatic Bubbly Flows Based on Averaged Flow Quantities for Use in Subchannel Codes

von Kommajosyula, Ravikishore
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 7 of 9 (2020)

ICONE28-65828 Heat Transfer Analysis of a Conceptual Horizontally-Oriented High Temperature Gas-Cooled Reactor

von Feng, Jinyong
Veröffentlicht in International Conference on Nuclear Engineering (28. : 2021 : Online) Proceedings of 2021 28th International Conference on Nuclear Engineering (ICONE 28) ; Volume 1: Operating plant challenges, successes, and lessons learned; nuclear plant engineering; advanced reactors and fusion; small modular and micro-reactors technologies and applications (2021)

Thermal Stratification Analysis in a Pool-Type Geometry

von Schneider, James
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 1 of 9 (2020)