Liquid lithium is a leading candidate as a tritium breeding material for fusion reactors because of its good breeding and heat-transfer characteristics. This paper describes a new experimental facility for investigating the corrosion/mass transfer/deposition mechanisms at characteristic velocities and system temperatures. This test facility, which is constructed of ferritic/martensitic steel (Fe-9Cr-1Mo), simulates conditions projected for a liquid metal heat transport system. The test facility will provide test velocities to 0.5 m/s, and temperatures to 550/degree/C, and system ..delta..T's up to 150/degree/C. The corrosion test region simulates the blanket region with a low inlet temperature and a higher (..delta..T /approximately/ 150/de...
Corrosion which is tolerable from the standpoint of system mechanical integrity may cause substantia...
As part of the Engineering Validation and Engineering Design Activities (EVEDA) phase for the Intern...
The application of liquid metal, especially liquid lithium, as a plasma facing component (PFC) has t...
Kinetics for grain boundary penetration and weight loss were determined for 304L stainless steel in ...
The use of ferritic/martensitic RAFM steels in PbLi blanket applications requires a better understan...
AbstractThe TechnoFusión project involves the construction of a relevant set of scientific-technical...
The design and implementation of future flowing liquid-lithium plasma-facing components (LLPFCs) wil...
The pyrochemical conditions of spent nuclear fuel for the purpose of final disposal is being demonst...
The use of low atomic number liquid metals has been shown to have the potential to solve many of the...
Tritium permeation into the Primary Heat Transfer System (PHTS) of DEMO and ITER reactors is one of ...
Liquid metal walls have been proposed to address the first wall challenge for fusion reactors. The L...
Solutions for the steady-state power exhaust problem in future fusion reactors (e.g. DEMO) are not a...
The corrosion of types 304L and 316 austenitic stainless steel by flowing lithium was studied in the...
As the fusion research community trends toward building larger and hotter devices, evidence points t...
The pyrochemical conditioning of spent nuclear fuel for the purpose of final disposal is currently b...
Corrosion which is tolerable from the standpoint of system mechanical integrity may cause substantia...
As part of the Engineering Validation and Engineering Design Activities (EVEDA) phase for the Intern...
The application of liquid metal, especially liquid lithium, as a plasma facing component (PFC) has t...
Kinetics for grain boundary penetration and weight loss were determined for 304L stainless steel in ...
The use of ferritic/martensitic RAFM steels in PbLi blanket applications requires a better understan...
AbstractThe TechnoFusión project involves the construction of a relevant set of scientific-technical...
The design and implementation of future flowing liquid-lithium plasma-facing components (LLPFCs) wil...
The pyrochemical conditions of spent nuclear fuel for the purpose of final disposal is being demonst...
The use of low atomic number liquid metals has been shown to have the potential to solve many of the...
Tritium permeation into the Primary Heat Transfer System (PHTS) of DEMO and ITER reactors is one of ...
Liquid metal walls have been proposed to address the first wall challenge for fusion reactors. The L...
Solutions for the steady-state power exhaust problem in future fusion reactors (e.g. DEMO) are not a...
The corrosion of types 304L and 316 austenitic stainless steel by flowing lithium was studied in the...
As the fusion research community trends toward building larger and hotter devices, evidence points t...
The pyrochemical conditioning of spent nuclear fuel for the purpose of final disposal is currently b...
Corrosion which is tolerable from the standpoint of system mechanical integrity may cause substantia...
As part of the Engineering Validation and Engineering Design Activities (EVEDA) phase for the Intern...
The application of liquid metal, especially liquid lithium, as a plasma facing component (PFC) has t...