Details

Autor(en) / Beteiligte

• Suk-Kwon Kim
• Jo, A. Ra
• Hyoung Gon Jin
• Eo Hwak Lee
• Jae-Sung Yoon
• Dong Won Lee
• Seungyon Cho

Titel

Current status of Korea heat load test facility for fusion reactor materials

Ist Teil von

• 2015 IEEE 26th Symposium on Fusion Engineering (SOFE), 2015, p.1-4

Ort / Verlag

IEEE

Erscheinungsjahr

2015

Quelle

IEEE Xplore

Beschreibungen/Notizen

• Korea heat load test facility by using electron beam (KoHLT-EB) was constructed and commissioned for the high heat flux test to verify the plasma facing components (PFCs), such as ITER first wall, tungsten divertor, and the heat transfer experiment. Also it will be used for ITER TBM (Test Blanket Module) performance test in Korea. The qualification tests will be performed to evaluate the high heat flux test facility for the PFC and fusion reactor materials. For the thermal fatigue test, two types of tungsten mock-ups were fabricated. One is a coated-tungsten on the ferritic-martensitic steel. The other is a bondedtungsten with ferritic-martensitic steel. Also, the integrity and cooling performance should be tested under the same or similar operation condition. After the completion of the preliminary mock-up test and facility qualification, the high heat flux test facility, KoHLT-EB, will assess the performance test for the various plasma facing components in fusion reactor materials and PFCs.