Results 1 to 10 of about 22,912 (217)

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

Nuclear 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, Satoshi Sato, Masayuki Ohta, Makoto Nakamura, Makoto Oyaidzu, Kentaro Ochiai, Atsushi Kasugai   +6 more
doaj   +3 more sources

Study of Structural and Strength Changes in Lithium-Containing Ceramics-Potential Blanket Materials for Nuclear Power, Subjected to High-Dose Proton Irradiation. [PDF]

Materials (Basel), 2022
Berguzinov A, Kozlovskiy AL, Khametova AA, Shlimas DI.   +3 more
europepmc   +2 more sources

Neutronic analysis of effects of inboard materials on the size of a tokamak fusion reactor

Nuclear Materials and Energy, 2021
The effects of inboard materials on the size of a tokamak fusion reactor were studied based on reactor system parameters determined through a coupled analysis of tokamak systems and neutron transport. With an inboard blanket, the shielding capability was
B.G. Hong, W. Cho
doaj   +1 more source

Study of Corrosion Resistance and Degradation Mechanisms in LiTiO₂-Li₂TiO₃ Ceramic

Crystals, 2021
The interest in lithium-containing ceramics is due to their huge potential as blanket materials for thermonuclear reactors for the accumulation of tritium.
Dmitriy Shlimas, Artem L. Kozlovskiy, Maxim Zdorovets   +2 more
doaj   +1 more source

Formation of Stable Lithium-Containing Ceramics Using Solid-Phase Synthesis Method

Crystals, 2021
Today, one of the most promising materials for a wide range of practical applications is lithium-containing ceramics based on Li2TiO3. At the same time, despite the high potential of their practical application, a number of questions remains related to ...
Dmitriy I. Shlimas, Artem L. Kozlovskiy, Maxim V. Zdorovets   +2 more
doaj   +1 more source

Study of Radiation Damage Processes Caused by Hydrogen Embrittlement in Lithium Ceramics under High-Temperature Irradiation

Ceramics, 2022
The aim of this work is to study the hydrogenation processes in lithium-containing ceramics under high-temperature irradiation. Irradiation was carried out with protons with an energy of 1 MeV and fluences of 1015–1017 ion/cm2 at irradiation temperatures
Dmitriy I. Shlimas, Artem L. Kozlovskiy, Maxim V. Zdorovets, Ainagul A. Khametova   +3 more
doaj   +1 more source

Three-dimensional thermal-hydraulics/neutronics coupling analysis on the full-scale module of helium-cooled tritium-breeding blanket

Nuclear Engineering and Technology, 2023
Blanket is of vital importance for engineering application of the fusion reactor. Nuclear heat deposition in materials is the main heat source in blanket structure.
Qiang Lian, Simiao Tang, Longxiang Zhu, Luteng Zhang, Wan Sun, Shanshan Bu, Liangming Pan, Wenxi Tian, Suizheng Qiu, G.H. Su, Xinghua Wu, Xiaoyu Wang   +11 more
doaj   +1 more source

Impact of blanket material and configuration on the size of a tokamak fusion reactor

Nuclear Materials and Energy, 2021
On the basis of the Korean fusion roadmap, conceptual design of the DEMO and R&D on the breeding blanket are ongoing. This article addresses the impact of blanket material and configuration on the tritium breeding, shielding characteristics, and ...
Bong Guen Hong
doaj   +1 more source

Preliminary study on Hot Isostatic Pressing diffusion bonding of Fe–Cr–Al and CLF–1 steel for preparation of tritium permeation barrier

Nuclear Materials and Energy, 2023
In the internal cooling channel forming of the blanket component for fusion reactor, the combination of Fe-Cr-Al ferritic steel with RAFM steel (reduced activation ferritic/martensitic steel) can form alumina film and then be served as tritium permeation
Pei-Song Du, Wan-Jing Wang, Ji-Chao Wang, Hua-Qi Xu, Qiao-ling Wang, Yu-Ping Xu, Hai-Shan Zhou, Wei Liu, Guang-Nan Luo   +8 more
doaj   +1 more source

Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material

Science and Technology of Nuclear Installations, 2022
Neutronic analysis in the HCLL blanket module has been established, and the calculation was performed by the ITER team, including the first wall (FW). In this study, seven materials have been investigated for FW material by considering characteristics ...
Indah Rosidah Maemunah, Zaki Su’ud, Abdul Waris, Dwi Irwanto   +3 more
doaj   +1 more source