DocumentCode :
61775
Title :
Manufacturing and Examination for ITER Blanket First Wall Small-Scale Mockups With KoHLT-EB in Korea
Author :
Suk-Kwon Kim ; Hyung Gon Jin ; Kyu In Shin ; Bo Guen Choi ; Eo Hwak Lee ; Jae-Sung Yoon ; Yang-Il Jung ; Dong Won Lee ; Duck-Hoi Kim
Author_Institution :
Korea Atomic Energy Res. Inst., Daejeon, South Korea
Volume :
42
Issue :
5
fYear :
2014
fDate :
May-14
Firstpage :
1438
Lastpage :
1442
Abstract :
The ITER first wall (FW) includes beryllium armor tiles joined to a CuCrZr heat sink. The FWs are one of the critical components in an ITER machine with a surface heat flux of 4.7 MW/m2 or above. The small-scale mockup shall be a part of the qualification tests and used to validate the performance of the dominant manufacturing technologies before the production of larger scale components, and this mockup shall be equipped with a hypervapotron heat sink and manufacturing processes developed for a semiprototype design. The small-scale mockup includes 48 beryllium armor tiles (12 mm × 12 mm) capable of withstanding the specified heat flux values. The tile thickness shall be 6 mm to minimize the beryllium surface temperature and evaporation under high thermal loads. The detailed fabrication process of semiprototype small-scale mockups was developed for a qualification test in Korea. For the CuCrZr and stainless steel, the canned materials are processed into an hot isostatic pressing (HIP) device. In the case of beryllium-to-CuCrZr joining, the HIP was conducted at 580°C and 100 MPa. For nondestructive tests of the fabricated semiprototypes, visual and dimension inspections were performed whenever needed during the fabrication process, and ultrasonic tests were performed using ultrasonic probes. Destructive tests for the qualification semiprototype were performed on a small-scale mockup, which was fabricated together with semiprototypes. The Korea heat load test facility using an electron beam system was constructed with an electron gun (maximum electric power of 800 kW) for a high heat flux application with a 300-kW high-voltage power supply and maximum accelerating voltage of 60 kV. This facility was operated to evaluate the performance test of plasma facing components. A cyclic heat flux test will be performed to evaluate the ITER qualification program.
Keywords :
Tokamak devices; armour; beryllium; chromium alloys; copper alloys; electron guns; fusion reactor blankets; heat sinks; hot pressing; inspection; plasma toroidal confinement; stainless steel; ultrasonic materials testing; zirconium alloys; Be-CuCrZr; ITER blanket first wall small-scale mockups; ITER machine; KoHLT-EB; Korea heat load test facility; beryllium armor tiles; beryllium surface temperature; canned materials; copper chromium zirconium heat sink; critical components; cyclic heat flux test; destructive testing; dimension inspection; dominant manufacturing technology; electron beam system; electron gun; evaporation; high thermal loads; hot isostatic pressing device; hypervapotron heat sink; joining materials; large scale component production; manufacturing process; maximum electric power; nondestructive testing; plasma facing components; power 300 kW; power 800 kW; pressure 100 MPa; qualification tests; semiprototype design; semiprototype small-scale mockups; size 6 mm; stainless steel; surface heat flux; temperature 580 degC; tile thickness; tokamak; ultrasonic probes; ultrasonic testing; visual inspection; voltage 60 kV; Beryllium; Cooling; Fabrication; Heating; Test facilities; High heat flux test; ITER first wall (FW); hot isostatic pressing (HIP); qualification test; qualification test.;
fLanguage :
English
Journal_Title :
Plasma Science, IEEE Transactions on
Publisher :
ieee
ISSN :
0093-3813
Type :
jour
DOI :
10.1109/TPS.2014.2312722
Filename :
6782647
Link To Document :
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