The SVBR-100 builds on the former Russian experience with lead-bismuth reactor technology used for several submarine propulsion units. It is a pool-type fast — spectrum reactor with forced circulation of the low-pressure primary coolant using two main circulation pumps. The initial core fuel is UO2 with a 235U enrichment below 20%, although subsequent fuel loads may contain U-Pu mixed oxide fuel or UN-PuN fuel. The core is composed of 61 fuel assemblies; however, a fresh core is loaded as a single cassette with whole-core replacement every eight years. Internal straight-tube steam generators are used to supply steam to external steam separators and a Rankine power-conversion unit. Although material corrosion issues plagued the early Russian submarine experience, corrosion problems were generally resolved by the conclusion of the earlier program.

The 100 MWe SVBR-100 is envisioned to supply both electricity and process heat for non-electrical applications. A single unit is expected to deliver 580 tons/h of process steam, 70 Gkal/h of district heat, or 200 000 tons/day of desalinated water if configured for these applications.

The SVBR-100 design effort was approved in 2006. A demonstration project was approved in 2011, at which time the reactor designer, OKB Gidropress, teamed with AKME Engineering to construct the first plant. Design and site licensing has been

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Figure 2.21 SVBR-100 (Russian Federation) — AKME Engineering/ОКБ Gildropress © AKME Engineering/OKB Gidropress.

ongoing since 2011 and approval was granted in 2013 with operations commencing in 2017. Key parameters and a representative graphic for the SVBR-100 design are given in Figure 2.21. [20]