ICONE28-66591 Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development

von Wang, Guogiang
Veröffentlicht in International Conference on Nuclear Engineering (28. : 2021 : Online) Proceedings of 2021 28th International Conference on Nuclear Engineering (ICONE 28) ; Volume 2: Nuclear fuels, research, and fuel cycle; nuclear codes and standards; thermal-hydraulics (2021)

Critical Heat Flux and Crud WALT Loop Measurements for Westinghouse Accident Tolerant Fuel

von Karoutas, Zeses
Veröffentlicht in Light Water Reactor Fuel Performance Conference (2019 : Seattle, Wash.) Light Water Reactor Fuel Performance Conference (TOP FUEL 2019) ; Volume 1 of 2 (2020)

Locked Rotor Studies to Quantify Benefits of Accident Tolerant Fuel Technologies

von Sung, Yixing
Veröffentlicht in Light Water Reactor Fuel Performance Conference (2019 : Seattle, Wash.) Light Water Reactor Fuel Performance Conference (TOP FUEL 2019) ; Volume 1 of 2 (2020)

CFD Modeling Development for DNB Prediction of Rod Bundle with Mixing Vanes under PWR Conditions

von Xu, Yiban
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 12 of 14 (2018)

Computational Fluid Dynamics Assessment of Baffle Plate Leakage Flow Effects in a Downflow 4-Loop Reactor

von Brewster, Robert A.
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 3 of 14 (2018)

Overview of Westinghouse Lead EnCore Accident Tolerant Fuel Program

von Oelrich, Robert
Veröffentlicht in Light Water Reactor Fuel Performance Conference (2019 : Seattle, Wash.) Light Water Reactor Fuel Performance Conference (TOP FUEL 2019) ; Volume 1 of 2 (2020)