Results 71 to 80 of about 628,084 (215)
Effect of divertor on tritium breeding in HELIAS
This study presents tritium breeding calculations for the five-period helical-axis advanced stellarator (HELIAS) using the Serpent2 code. To address the absence of a detailed divertor design, a simplified divertor model with a layered homogenized structure was integrated into the parametric geometry of the HELIAS.
Lyytinen, Tommi +3 more
openaire +2 more sources
Intranasal (IN) delivery of PEGylated PLGA nanoparticles (NPs) loaded with oxytocin (OT) (OT‐NP‐PEG) is investigated as a strategy to enhance OT transport to the brain for treating autism and other neuropsychiatric disorders. The optimized NP formulation demonstrates appropriate physicochemical characteristics, improved stability, and enhanced mucosal ...
Naveed Ahmad +11 more
wiley +1 more source
Tracer Hydrology Practices, Challenges, and Opportunities Across Latin America and the Caribbean
Tracer monitoring characteristics across the LAC region: overview of sampled hydrologic systems, commonly used tracers, routine and event‐based sampling strategies, integration with hydrometric measurements, and monitoring durations. ABSTRACT Tracer hydrology in Latin America and the Caribbean has made significant progress in recent decades, largely ...
Ricardo Sánchez‐Murillo +47 more
wiley +1 more source
Tritium Breeding Ceramics for Nuclear Fusion
Tritium and deuterium are widely considered as fuel for fusion power plants. While deuterium is quite abundant in nature, tritium needs to be “bred” from lithium in a neutron reaction. Hence, for the breeding blanket development of the International Thermonuclear Experimental Reactor (ITER) and the DEMOnstration power plant (DEMO), the development of ...
Leys, Julia +2 more
openaire +1 more source
Tritium self-sufficiency is a critical prerequisite for future fusion reactors. The tritium breeding blanket, as the component responsible for in-vessel tritium generation, requires coordinated neutronic and engineering optimization in order to maximize ...
Shen Qu +6 more
doaj +1 more source
Helium-Cooled Ceramic Breeding Blanket Module(HCCB-TBM) will be installed on ITER machine to test its tritium breeding performance and thermal removal ability.
WANG Jun +4 more
doaj +1 more source
The Chinese Fusion Engineering Test Reactor (CFETR) is a tokamak device located between ITER and DEMO, with the primary goal of generating useable fusion energy through D–T reactions.
Jie Li +4 more
doaj +1 more source
Preparation of Li2TiO3-Li4SiO4-Pb tritium breeding ceramic and its mechanical properties
Qiao Wang +6 more
semanticscholar +1 more source
A study on double-layer neutron reflector for tritium breeding unit in test facility
The long-term performance verification of the Breeding Blanket (BB) considering continuous plasma operation is essential to develop fusion power reactor.
Do Hyun Kim, Hyoseong Gwon, Mu-Young Ahn
doaj +1 more source
Fusion technologies for Laser Inertial Fusion Energy (LIFE)∗
The Laser Inertial Fusion-based Energy (LIFE) engine design builds upon on going progress at the National Ignition Facility (NIF) and offers a near-term pathway to commercial fusion.
Kramer K.J. +12 more
doaj +1 more source

