Applicability of Steam-Explosion Retardant for Molten Nickel and Tin at High-Temperature

von Furuya, Masahiro
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 2 of 14 (2018)

Data Assimilation with Subchannel Analysis Code CTF on NUPEC BWR BFBT Test Matrix

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

Accident Progression Analyses of a BWR with Filtered Containment Venting System During Long Term Severe Accident Conditions

von Ui, Atsushi
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 13 of 14 (2018)

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (1) Project Overview

von Yamano, Hidemasa
Veröffentlicht in International Nuclear Fuel Cycle Conference (2019 : Seattle, Wash.) International Nuclear Fuel Cycle Conference (GLOBAL 2019) ; Volume 1 of 2 (2020)