Abstract
One of the main technology missions of a fusion nuclear science facility (FNSF) is to validate the performance of an integrated set of in-vessel components in prototypical fusion operating conditions prior to inclusion in demonstration and/or first-of-a-kind power plant. The FNSF developed by Princeton Plasma Physics Laboratory will enable such integral testing of fusion technologies. The blanket testing and development strategy requires access for a number of test blanket modules (TBMs) and a base blanket installed in the available space surrounding the TBMs and heating/CD ports. A unique feature of the proposed strategy is that the TBMs play a key role and serve as forerunners for a more advanced version of the base blanket. The maximum achievable tritium breeding ratio (TBR), the shielding of all magnets, and the radial build definition are among the numerous design issues investigated in detail. Potential means to increase the TBR were also investigated.
| Original language | English (US) |
|---|---|
| Article number | 6804011 |
| Pages (from-to) | 1457-1463 |
| Number of pages | 7 |
| Journal | IEEE Transactions on Plasma Science |
| Volume | 42 |
| Issue number | 5 |
| DOIs | |
| State | Published - May 2014 |
All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- Condensed Matter Physics
Keywords
- Blanket testing strategy
- fusion nuclear science facility (FNSF)
- neutron wall loading distribution
- radial build
- tritium breeding ratio (TBR)
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