Abstract
The nuclear engineering infrastructure of port-based diagnostics on ITER is presented, including the equatorial and upper port plug generic designs, the adopted modular concept, the loads and associated load response and the remote handling. A modular approach is adopted for the internal shielding modules as this helps to reduce the dominant electromagnetic loads, reduces interfaces and accelerates remote handling. Extensive use of gun-drilling is employed to produce water channels in the stainless steel plate and forgings used to construct the port plugs and modules. The French Nuclear Code RCC-MR (2007) is employed in the design and the manufacturing. An integrated remote handling scheme is described, including a description of maintenance operations in the Hot Cell Facility.
| Original language | English (US) |
|---|---|
| Pages (from-to) | 667-674 |
| Number of pages | 8 |
| Journal | Fusion Engineering and Design |
| Volume | 87 |
| Issue number | 5-6 |
| DOIs | |
| State | Published - Aug 2012 |
All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Nuclear Energy and Engineering
- General Materials Science
- Mechanical Engineering
Keywords
- Diagnostics
- ITER
- Nuclear shielding
- Port plugs
- Remote handling
- Shut-down dose rate