Results 21 to 30 of about 79,921 (199)

Analysis of fuel rejuvenation times in a fusion breeder reactor fuelled with a mixture of uranium-thorium oxides for the CANDU reactor [PDF]

open access: yesNuclear Technology and Radiation Protection, 2017
This study presents the determination of fuel rejuvenation times in a D-T fusion breeder reactor fuelled with a mixture of natUO2 and ThO2 for multi-reuse of nuclear fuels in CANDU-37 reactors.
Bakir Gizem, Yapici Huseyin
doaj   +1 more source

Electrochemical deposition of La-Mg alloys in LaCl3-MgCl2-KCl system with molten salt electrolysis process [PDF]

open access: yesJournal of Mining and Metallurgy. Section B: Metallurgy, 2014
La-Mg alloys of different compositions were prepared by electrolysis of LaCl3-MgCl2-KCl melts. Different phases of La-Mg alloys were characterized by X-ray diffraction (XRD) and Scanning Electron Microscopy (SEM). Energy dispersive spectrometry (
Sahoo Kumar D.   +2 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

Considering for the blanket structure scheme of HCCB DEMO

open access: yesTheoretical and Applied Mechanics Letters, 2019
: For the solid blanket concept of helium cooled ceramic breeder (HCCB) demonstration fusion power plant (DEMO), a feasible blanket structure with configuration 2×X is proposed as considering relatively low temperature limit of neutron multiplier ...
Zhou Zhao   +4 more
doaj   +1 more source

Tritium supply and use: a key issue for the development of nuclear fusion energy [PDF]

open access: yes, 2018
Full power operation of the International Thermonuclear Experimental Reactor (ITER) has been delayed and will now begin in 2035. Delays to the ITER schedule may affect the availability of tritium for subsequent fusion devices, as the global CANDU-type ...
Armando B. Antoniazzi   +38 more
core   +1 more source

Shielding efficiency of metal hydrides and borohydrides in fusion reactors [PDF]

open access: yesNuclear Technology and Radiation Protection, 2016
Mass attenuation coefficients, mean free paths and exposure buildup factors have been used to characterize the shielding efficiency of metal hydrides and borohydrides, with high density of hydrogen.
Singh Vishvanath P.   +2 more
doaj   +1 more source

Optimal Radial Build and Transmutation Properties of a Fusion-Based Transmutation Reactor with Molten Salt Coolants

open access: yesEnergies, 2022
The optimal shape of a fusion-based transmutation reactor with a molten salt coolant was determined by plasma physics, technology, and neutronic requirements.
Bong-Guen Hong
doaj   +1 more source

Recent Fusion Research in the National Institute for Fusion Science [PDF]

open access: yes, 2011
The National Institute for Fusion Science (NIFS), which was established in 1989, promotes academic approaches toward the exploration of fusion science for steady-state helical reactor and realizes the establishment of a comprehensive understanding of ...
Akio KOMORI   +6 more
core   +2 more sources

Activation analysis and waste management for dual functional lithium-lead blanket of the China Fusion Engineering Test Reactor

open access: yesFushe yanjiu yu fushe gongyi xuebao, 2021
Based on the design requirements of the first stage of the China Fusion Engineering Test Reactor (CFETR), the activation performance calculation and analysis of the components in the dual function lead-lithium blanket were performed using a neutron ...
ZENG Zhengkui   +5 more
doaj   +1 more source

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

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