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

P3.133 Shutdown dose rate assessment during replacement of in-vessel components for a fusion DEMO reactor

7 Sep 2016, 11:00
1h 20m
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: 133
Poster G. Vessel/In-Vessel Engineering and Remote Handling P3 Poster session

Speaker

Youji Someya (Sector of fusion research and development)

Description

Periodical replacement of in-vessel components is required for DEMO. The surface dose rate of in-vessel components for DEMO with fusion power of 1.5 GW is higher than that of shielding blanket in ITER by double digits. In addition, DEMO requires five-year cooling time for decreasing its dose rate to the level of ITER. Therefore, it is difficult to adopt the in-vessel maintenance scheme as ITER in terms of plant availability. To consider a maintenance process for DEMO, 3D shutdown dose rate map was analysed with MCNP-5 and DCHAIN-SP2001. The operation time of blanket (F82H) and divertor (W mono-block) is assumed to be 4 years and 1 year, respectively. The proposed maintenance scheme has an assumption that blanket integrated with shielding block (SB) is replaced through a vertical upper port whereas divertor also integrated with SB is replaced through a bottom port. To reduce dose rate, robot arm should approach from behind a SB and be fixed with an attachment of the SB. Based on the scheme, the dose rate in each maintenance port was evaluated. Before replacement, the spatial dose rate in a maintenance port for blanket and for divertor at the beginning of maintenance was 0.01 Gy/h and 0.1 Gy/h, respectively. When the divertor with the SB was removed, the spatial dose rate in each maintenance port was 100 Gy/h. After the replacement with new equipment, the dose rate in each maintenance port would be 10 Gy/h. The spatial dose rate in vacuum vessel of ITER during maintenance is determined as 250 Gy/h according to the requirement for remote handling of shielding blanket. The proposed maintenance scheme can limit the use of remote equipment only in a maintenance port leading to the reduction of the dose rate in the maintenance area for DEMO in comparison with ITER.

Co-authors

Hiroyasu Utoh (Sector of fusion research and development, Japan Atomic Energy Agency, Kamikita-gun, Aomori, Japan) Hisashi Tanigawa (Sector of fusion research and development, Japan Atomic Energy Agency, Kamikita-gun, Aomori, Japan) Kenji Tobita (Sector of fusion research and development, Japan Atomic Energy Agency, Kamikita-gun, Aomori, Japan) Ryoji Hiwatari (Sector of fusion research and development, Japan Atomic Energy Agency, Kamikita-gun, Aomori, Japan) Youji Someya (Sector of fusion research and development, Japan Atomic Energy Agency, Kamikita-gun, Aomori, Japan)

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