5-9 September 2016
Prague Congress Centre
Europe/Prague timezone

P4.125 Investigation on feasibility of cleanliness assessment using test sample for ITER blanket shield block

8 Sep 2016, 14:20
1h 40m
Foyer 2A (2nd floor), 3A (3rd floor) (Prague Congress Centre)

Foyer 2A (2nd floor), 3A (3rd floor)

Prague Congress Centre

5. května 65, Prague, Czech Republic
Board: 125
Poster F. Plasma Facing Components P4 Poster session

Speaker

Hun-Chea Jung (ITER Korea)

Description

The ITER blanket shield block (SB) is one of the in-vessel components, which is designed to provide nuclear shielding and to supply the cooling water to vacuum vessel and external component. The ITER SB is classified the VQC 1A as vacuum classification and its manufacturing process and cleaning procedure shall comply with the ultra-high vacuum conditions necessary for machine operation and follow the requirements of the ITER Vacuum Handbook (VHB). And also the ITER SB shall be properly cleaned and dried before packaging and be ensured its cleanliness in accordance with ITER VHB. According to ITER VHB, cleanliness of vacuum components shall be verified with the wipe test and outgassing rate measurement. For wipe test, it is difficult to assess the quantitative cleanliness of vacuum components due to its subjective nature. Accordingly, the outgassing rate measurement may be needed for assessment of cleanliness for ITER SB. However, it is impossible to perform the outgassing rate measurement of ITER SB because additional activities, such as machining and any treatment, are prohibited after final cleaning process. Therefore, it needs to verify the satisfaction with cleanliness of ITER SB by using test samples. The objective of this study is to investigate the feasibility of cleanliness assessment by outgassing rate measurement using test samples for establishment of test procedure. The effect of cleaning method on the outgassing rate also investigated. The outgassing rate was measured at 100ooC for 10hrs in accordance with ITER VHB.

Co-authors

Hee-Jin Shim (ITER Korea, National Fusion Research Institute, Daejeon, South Korea) Hun-Chea Jung (ITER Korea, National Fusion Research Institute, Daejeon, South Korea) Min-Su Ha (ITER Korea, National Fusion Research Institute, Daejeon, South Korea) Sa-Woong Kim (ITER Korea, National Fusion Research Institute, Daejeon, South Korea)

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