Results 21 to 30 of about 20,199 (310)

Effects of Constrictor Geometry, Arc Current, and Gas Flow Rate on Thermal Plasma Characteristics in a Segmented Arc Heater

open access: yesJournal of Thermal Science and Technology, 2011
A numerical simulation on a segmented arc heater which is used to generate high thermal flow environments for the test of heat shield materials, were carried out.
Sooseok CHOI   +3 more
doaj   +1 more source

Fusion Reactor Design Studies [PDF]

open access: yesScience, 1976
This progress report will give a detailed breakdown of the work accomplished for ARIES-III during the contract period, November 1, 1990 to October 31, 1991. The areas of effort discussed are: Neutronics; First-Wall; Shield; Safety; Systems; Startup and Shutdown; Energy Conversion; Ripple Loss; and Fuel Resources.
R W, Conn, G L, Kulcinski
openaire   +2 more sources

Shutdown Dose Rate Analysis for the long-pulse D-D Operation Phase in KSTAR

open access: yesEPJ Web of Conferences, 2017
KSTAR is a medium size fully superconducting tokamak. The deuterium-deuterium (D-D) reaction in the KSTAR tokamak generates neutrons with a peak yield of 3.5x1016 per second through a pulse operation of 100 seconds.
Park Jin Hun   +4 more
doaj   +1 more source

Engineering Application of Fusion Reactors in China: Problems and Strategies [PDF]

open access: yes中国工程科学
Breakthroughs in nuclear fusion technologies are expected to revolutionize energy production and generate substantial economic benefits, emerging as a key medium-to-long-term development focus in global science, technology, and energy domains.
Jingwu Wen   +5 more
doaj   +1 more source

Recent Progress in the Numerical Simulation Reactor Research Project [PDF]

open access: yes, 2019
0000-0001-5444-1758Fusion plasmas are complex systems which involve a variety of physical processes interacting with each other across wide ranges of spatiotemporal scales.
SUGAMA, Hideo   +1 more
core   +2 more sources

The EU programme for modelling radiation effects in fusion reactor materials [PDF]

open access: yes, 2011
S.1-7The EU fusion materials modelling programme was initiated in 2002 with the objective of developing a comprehensive set of computer modelling techniques and approaches, aimed at rationalising the extensive available experimental information on ...
Lavrentiev, M.Y.   +18 more
core   +1 more source

Preparation of V–4Cr–4Ti Alloys from Mixed Oxides via Electro-Deoxidation Process in Molten Salt

open access: yesMetals, 2020
V–4Cr–4Ti alloys exhibit important advantages as a candidate structural materials for fusion reactor first-walls and blanket applications. V–4Cr–4Ti alloys were prepared by direct electrochemical reduction of the solid mixture of V2O3, Cr2O3 and TiO2 in ...
Xiaozhou Cao   +4 more
doaj   +1 more source

Simulation study of tritium atmospheric dispersion of loss of vacuum accident of a fusion reactor

open access: yesHe jishu, 2023
BackgroundTritium can be released into the environment in a loss of vacuum (LOVA) scenario in a fusion reactor. The simulation of the atmospheric dispersion behaviour of tritium is one of the core components of the assessment of the radioactive ...
JIANG Jinghua, CAO Xuewu
doaj   +1 more source

Conceptual design of DEMO blanket materials test modules for A-FNS

open access: yesNuclear Materials and Energy, 2020
A conceptual design of Advanced Fusion Neutron Source, A-FNS, has been conducted to achieve early realization of fusion-like neutron irradiation test for fusion reactor materials in Japan.
Saerom Kwon   +6 more
doaj   +1 more source

Development of Strategic Establishment of Technology Bases for a Fusion DEMO Reactor in Japan [PDF]

open access: yes, 2016
0000-0003-4546-3167The strategic establishment of technology bases required for the development of a fusion demonstration reactor (DEMO) has been discussed by joint endeavors throughout the Japanese fusion community.
OKANO, Kunihiko   +11 more
core   +2 more sources

Home - About - Disclaimer - Privacy