Recrystallization, cracking, and erosion of dispersoid-strengthened tungsten materials during exposure to divertor plasmas
Nuclear Materials and Energy
Nuclear Materials and Energy
Publications
Search results
Jump to search filtersRecrystallization, melting, and erosion of dispersoid-strengthened tungsten materials during exposure to DIII-D plasmas
Abstract not provided.
3D Heat Flux and Melt Motion Analysis of Angled Tungsten Samples on DIII-D
Abstract not provided.
Failure of a lithium-filled target and some implications for fusion components
Fusion Engineering and Design
In preparation for testing a lithium-helium heat exchanger at Sandia, unexpected rapid failure of the mild steel lithium preheater due to liquid metal embrittlement occurred when lithium at ~400 °C flowed into the preheater then at ~200 °C. This happened before the helium system was pressurized or heating with electron beams began. The paper presents an analysis of the preheater plus a discussion of some implications for fusion.
Additively Manufactured Tungsten Samples for DIII-D DiMES Experiments
Abstract not provided.
Additively Manufactured Tungsten Samples for DIII-D DiMES Experiments
Abstract not provided.
DESIGN INTEGRATION ISSUES FOR LIQUID SURFACE PFCS IN A COMPACT PILOT PLANT
Abstract not provided.
LIQUID METAL EMBRITTLELENT OF A Li-FILLED FERRITIC TARGET - IMPLICATIONS FOR FUSION COMPONENTS
Abstract not provided.
Post-test examination of a Li-Ta heat pipe exposed to H plasma in Magnum PSI
Fusion Engineering and Design
The authors exposed a radiatively cooled, Li-filled tantalum (Ta) heat pipe (HP) to a H plasma in Magnum PSI continuously for ˜2 h. We kept the overall heat load on the inclined HP constant and varied the tilt to give peak heat fluxes of ˜7.5–13 MW/m2. The peak temperature reached ˜1250 °C. This paper describes the post-test analysis and discusses Li HPs with materials other than Ta for fusion. A companion paper describes the experiment.
A (my) Perspective on the US Fusion Technology R&D Path Toward Fusion Energy
Abstract not provided.
Fusion Technology Wolves Wanderings and Thoughts on Your Future
Abstract not provided.
A Perspective on the US Fusion Technology R&D Path Toward Fusion Energy
Abstract not provided.
A Perspective on the US Fusion Technology R&D Path Toward Fusion Energy
Abstract not provided.
NygrenORNLWkshp2019-Blanket_Systems_Integration_Thrust
Abstract not provided.
BlanketWorkshopORNLjan2019-Blanket_FW_Protection_Thrust
Abstract not provided.
NygrenORNLWkshp2019-Innovative_Capabilities_for_Fuel_Cycle_Thrust
Abstract not provided.
BlanketWorkshopORNLjan2019-Integration_Fuel_Cycle_Components
Abstract not provided.
Power Deposition on a Tungsten Leading Edge in a DIII-D He Plasma
Abstract not provided.
Innovation First - Technology
Abstract not provided.
Power Deposition on a Tungsten Leading Edge in a DIII-D He Plasma
Abstract not provided.
Advanced Manufacturing ? A Transformative Enabling Capability for Fusion
Abstract not provided.
Developing Fusion Subcomponents with Additive Manufacturing
Abstract not provided.
ELM Heat Loads in 2016 DiMES W Leading Edge Experiments
Abstract not provided.
Advanced Manufacturing ? A Transformative Enabling Capability for Advancing Fusion
Abstract not provided.
Liquid surfaces for fusion plasma facing components—A critical review. Part I: Physics and PSI
Nuclear Materials and Energy
This review of the potential of robust plasma facing components (PFCs) with liquid surfaces for applications in future D/T fusion device summarizes the critical issues for liquid surfaces and research being done worldwide in confinement facilities, and supporting R&D in plasma surface interactions. In the paper are a set of questions and related criteria by which we will judge the progress and readiness of liquid surface PFCs. Part-II (separate paper) will cover R&D on the technology-oriented aspects of liquid surfaces including the liquid surfaces as integrated first walls in tritium breeding blankets, tritium retention and recovery, and safety.
Results 1–25 of 99