ICONE2020-16838 Two-Dimensional Full Core Analysis of IFBA-Coated TRISO Fuel Particles in Very High Temperature Reactors

von Alrwashdeh, Mohammad
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)

A Mixed Convection Heat Transfer Benchmark Test Case: the Prismatic-Core Advanced High Temperature Reactor

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

Optimization of Heat Transfer Rate Around Cylindrical PCM Containers in Energy Storage Coupled with Nuclear Power Plant

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

PARTNERING BETWEEN THE IAEA COLLABORATION CENTER FOR HUMAN RESOURCE AND NUCLEAR ENERGY INFRASTRUCTURE DEVELOPMENT & GULF NUCLEAR ENERGY INFRASTRUCTURE INSTITUTE (GNEII)

von Williams, Adam D.
Veröffentlicht in Institute of Nuclear Materials Management (60. : 2019 : Palm Desert, Calif.) 60th Annual Meeting of the Institute of Nuclear Materials Management (INMM 2019) ; Volume 2 of 3 (2020)