Study on melting and solidification behaviors of tungsten loaded by high heat flux for divertor in tokamak fusion reactor

2018 ◽  
Vol 136 ◽  
pp. 350-356 ◽  
Author(s):  
Eiji Hoashi ◽  
Shinpei Kuroyanagi ◽  
Takafumi Okita ◽  
Takeru Maeji ◽  
Kenzo Ibano ◽  
...  
2007 ◽  
Vol 16 (1) ◽  
pp. 96-103 ◽  
Author(s):  
Kendall J. Hollis ◽  
Brian D. Bartram ◽  
Manfred Roedig ◽  
Dennis Youchison ◽  
Richard Nygren

2010 ◽  
Vol 63 ◽  
pp. 383-391
Author(s):  
Chang Chun Ge ◽  
Shuang Quan Guo ◽  
Yun Biao Feng ◽  
Zhang Jian Zhou ◽  
Juan Du ◽  
...  

Different coating technologies, such as plasma spray (PS), physical vapor deposition (PVD) and chemical vapor deposition (CVD), which can fabricate the PFM and join it to heat sink materials simultaneously, were applied for the fabrication of plasma facing materials (PFM) in fusion reactor. In the Institute of Nuclear Materials, University of Science and Technology Beijing (USTB), the concept of functionally graded materials (FGM) was adopted to fabricate coatings for effectively alleviating the thermal stress generated between coatings and the substrate materials under high heat flux loading (5~20 MW/m2). In the last several years, functionally graded coatings, including B4C/Cu, W/Cu and Mo/Cu systems were successfully fabricated by atmospheric plasma spray (APS). Characterization of coatings was performed in order to assess microstructure, mechanical properties and high heat flux properties of the FGM coatings. Furthermore, a high thick tungsten coating with 4 mm on copper – chromium - zirconium (Cu, Cr, Zr) alloy substrates was fabricated by APS. The porosity of the coating is less than 2% while mean tensile strength of the coating is about 7 MPa. However, the content of oxygen in the coating is about 6 wt% by energy dispersive spectrum (EDS) analysis, thus further optimization is necessary.


Energies ◽  
2019 ◽  
Vol 12 (19) ◽  
pp. 3771
Author(s):  
Lee ◽  
Kim ◽  
Moon ◽  
Lim ◽  
Cho

Nuclear fusion energy is a solution to the substitution of fossil fuels and the global energy deficit. However, among the several problems encountered for realizing a nuclear fusion reactor, the divertor presents difficulties due to the tremendous heat flux (~10 MW/m2) from high-temperature plasma. Also, neutrons produce additional heat (~17.5 MW/m3) from collisions with the materials’ atoms. This may lead to unexpected effects such as thermal failure. Thus, a comprehensive investigation on the divertor module is needed to determine the heat-absorbing capacity of the divertor module so to maintain the effect of incident heat flux. In this study, using an analytical approach and a simulation, the quantitative effect of heat generation on the thermophysical behavior, such as temperature and thermal stress, was analyzed while maintaining the incident heat flux. Then, a correlated equation was derived from the thermal design criteria, namely, the maximum thimble temperature and the safety factor at the vulnerable point. Finally, on the basis of the thermal design criteria, the heat-absorbing capacity of a nuclear fusion reactor in operating conditions was determined. This study contributes to the understanding of the divertor’s effects in nuclear fusion reactors for high-heat-flux and high-temperature applications.


1995 ◽  
Vol 28 ◽  
pp. 119-124
Author(s):  
B.A Kahn ◽  
V.T Fedotov ◽  
A.E Grigoriev ◽  
O.N Sevriukov ◽  
A.N Pliushev ◽  
...  

2021 ◽  
Vol 54 (5) ◽  
Author(s):  
F. Schoofs ◽  
S. King ◽  
A. J. Cackett ◽  
M. Leyland ◽  
C. Hardie

Small-angle neutron scattering (SANS) is performed to analyse the microstructural state of a reference CuCrZr material with carefully controlled heat treatments, small-scale manufacturing mock-ups of assemblies and high-heat-flux-exposed mock-ups for fusion reactor components. The information derived from the SANS data corresponds well to existing literature data based on microscopic-scale techniques, but is obtained at millimetre scale with minimal surface preparation. The manufacturing method and high-heat-flux testing conditions are confirmed to have little impact on the microstructural properties, demonstrating the validity of these treatments for scaled-up reactor components.


2015 ◽  
Vol 55 (2) ◽  
pp. 86-95 ◽  
Author(s):  
Phani Kumar Domalapally ◽  
Slavomir Entler

Some components of the fusion reactor receives high heat fluxes either during the startup and shutdown or during the operation of the machine. This paper analyzes different ways of enhancing heat transfer using helium and water for cooling of these high heat flux components and then conclusions are drawn to decide the best choice of coolant, for usage in near and long term applications.


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