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The KO HCCR TBM (Korean Helium Cooled Ceramic Reflector Test Blanket Module) was consisted of 4 sub-modules. A thermal-structural analysis of the changed FW design, which has a 15 × 11 rectangular U-shape, was carried out according to the RCC-MR code considered the design pressure (10 MPa) and thermal stress results based on the thermal-hydraulic analysis. The contact stress between the TBM sub-modules was also evaluated to confirm the structural integrity. The results showed that the design requirements were satisfied.

The ITER first wall (FW) includes beryllium armour tiles joined to a CuCrZr heat sink with stainless steel cooling tubes. The FW panels 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 part of the qualification program and used to validate the performance of the key manufacturing technologies before the production of larger scale components, and this mockup shall utilize the hypervapotron heat sink and manufacturing processes developed for a semi-prototype design. The small-scale mockup includes 48 beryllium armour 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 semi-prototype small-scale mockups was developed for a qualification test in Korea. For the CuCrZr and stainless steel, the canned materials are processed into an HIP (Hot Isostatic Pressing) device. In the case of beryllium to CuCrZr joining, the HIP was conducted at 580 °C and 100 MPa. For non-destructive tests of the fabricated semi-prototypes, visual and dimension inspections were performed whenever needed during the fabrication process, and ultrasonic tests were performed with ultrasonic probes. Destructive tests for the qualification semi-prototype were performed on a small mockup, which was fabricated together with semi-prototypes. The Korea heat load test facility, KoHLT-EB (Electron Beam) was constructed with an electron gun (Max. 800 kW) for a high heat flux application with a 300 kW high voltage power supply, and maximum accelerating voltage of 60 kV. This test facility was operated to evaluate the performance of these small-scale mockups. A cyclic heat flux test will be performed to evaluate the ITER qualification program.

Korea has developed a Helium Cooled Ceramic Reflector (HCCR) Test Blanket Module (TBM) for testing in ITER and it consists of the functional components to distribute the He coolant to each region such as First Wall (FW), Breeding Zone (BZ), Side Wall (SW), and Back Manifold (BM). In the current study, the detailed design of each components were introduced as follows; (1) FW considering cooling under structural material temperature limit (550 °C); (2) BZ layer for obtaining tritium breeding ratio and cooling with breeder, reflector, and multiplier pebbles; (3) SW considering the flow distribution to BZ and internal pressure; (4) BM for uniform flow to FW cooling channels; and (5) He purge line in BZ considering purge gas distribution in BZ. From the analysis with the CFD code, ANSYS-CFX with the results of nuclear heating by neutronic analysis, the performances of each functional components were investigated and it is confirmed that their performances were satisfied the design requirements of KO HCCR TBM.