Heat load test of Be/Cu joint for ITER first wall mock-ups

2002 ◽  
Vol 307-311 ◽  
pp. 1533-1536 ◽  
Author(s):  
M. Uchida ◽  
E. Ishitsuka ◽  
T. Hatano ◽  
V. Barabash ◽  
H. Kawamura
Keyword(s):  
Heat Load ◽  
Load Test ◽  
First Wall

Fabrication Methods Development for the Korea TBM First Wall in the ITER

2010 ◽  
Author(s):  
Dong Won Lee ◽  
Young Dug Bae ◽  
Suk Kwon Kim ◽  
Jae Sung Yoon ◽  
Bong Guen Hong ◽  
...  
Keyword(s):  
Heat Load ◽  
Martensitic Steel ◽  
High Heat ◽  
Heat Fluxes ◽  
Load Test ◽  
High Heat Flux ◽  
First Wall ◽  
Methods Development ◽  
Molten Lithium ◽  
The Republic

The Republic of Korea has proposed and designed a helium cooled molten lithium (HCML) test blanket module (TBM) to be tested in the ITER. Ferritic Martensitic Steel (FMS) and beryllium are designed to be used as structural material and armor for the TBM first wall (FW) in this design, respectively. In order to develop the fabrication method for the TBM FW, the joining methods of FMS to FMS and Be to FMS have been developed with hot istotatic pressing (HIP). For joining FMS to FMS, mock-ups were fabricated with an HIP (1050 °C, 100 MPa, 2 hours). For joining Be to FMS, two mock-ups were fabricated with the same method (580 °C, 100 MPa, 2 hours) using different interlayers. Then, in order to evaluate the integrity of the fabricated mock-ups, they were tested at the high heat flux (HHF) test facilities, KoHLTs (Korea Heat Load Test) under 1.0 MW/m2 and 0.5 MW/m2 heat fluxes of up to 1000 cycles.

scholarly journals Erratum to “Radiative heat load distribution on the EU-DEMO first wall due to mitigated disruptions” [Nucl. Mater. Energy 25 (2020) 100824]

2021 ◽  
Vol 27 ◽  
pp. 100978
Author(s):  
M. Moscheni ◽  
M. Carr ◽  
S. Dulla ◽  
F. Maviglia ◽  
A. Meakins ◽  
...  
Keyword(s):  
Load Distribution ◽  
Heat Load ◽  
Radiative Heat ◽  
First Wall ◽  
The Eu

Current Status of Korea Heat Load Test Facility KoHLT-EB for Fusion Reactor Materials

2017 ◽  
Vol 45 (7) ◽  
pp. 1820-1823
Author(s):  
Suk-Kwon Kim ◽  
Seong Dae Park ◽  
Hyoung Gon Jin ◽  
Eo Hwak Lee ◽  
Jae-Sung Yoon ◽  
...  
Keyword(s):  
Heat Load ◽  
Fusion Reactor ◽  
Load Test ◽  
Test Facility ◽  
Current Status ◽  
Reactor Materials

High heat load experiments for first wall materials

1988 ◽  
Vol 155-157 ◽  
pp. 402-406 ◽  
Author(s):  
H. Yanagi ◽  
T. Sukegawa ◽  
K. Kobayashi ◽  
H. Madarame ◽  
H. Hashizume ◽  
...  
Keyword(s):  
Heat Load ◽  
High Heat ◽  
First Wall ◽  
High Heat Load ◽  
Wall Materials

Development and heat load experiments of graphite brazed to stainless steel for the first wall structure of FER

1989 ◽  
Vol 9 ◽  
pp. 283-287 ◽  
Author(s):  
K. Ioki ◽  
M. Nayama ◽  
S. Tsujimura ◽  
M. Seki ◽  
T. Horie
Keyword(s):  
Stainless Steel ◽  
Heat Load ◽  
Wall Structure ◽  
First Wall

High heat load tests of a graphite armor first wall with a water cooling jacket

1989 ◽  
Vol 9 ◽  
pp. 289-294 ◽  
Author(s):  
Yoshitaka Gotoh ◽  
Hisanori Okamura ◽  
Shin-ichi Itoh ◽  
Takeshi Wada ◽  
Yoshinori Karatsu
Keyword(s):  
Heat Load ◽  
High Heat ◽  
Water Cooling ◽  
First Wall ◽  
Load Tests ◽  
High Heat Load ◽  
Cooling Jacket

scholarly journals High heat load experiments for first wall materials by high power ion beams.

1985 ◽  
Vol 54 (3) ◽  
pp. 371-384 ◽  
Author(s):  
Tsutomu Kuroda ◽  
Osamu Kaneko ◽  
Keiichi Sakurai ◽  
Yoshihide Oka ◽  
Masanao Shibui ◽  
...  
Keyword(s):  
High Power ◽  
Heat Load ◽  
High Heat ◽  
Ion Beams ◽  
First Wall ◽  
High Heat Load ◽  
Wall Materials
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