Fig 1.
The nuclear reactor development in S-curves.
Fig 2.
(Right): Simplified scheme of the MSFR system including the core, blanket and heat exchangers (IHX)–(Left): Benchmark definition [13].
Fig 3.
Volume corrected 2D HELIOS model of the molten salt reactor.
Fig 4.
Description of the calculation cycle for the simulation of a MSR.
Fig 5.
Change of the deviation of the averaged effective multiplication factor over a simulated operational period of 80 years within the iteration band of ±400 pcm.
Fig 6.
Number density of the different Pu isotope particles in the fuel salt over the observed operational period.
Fig 7.
Number density of the relevant Neptunium and Americium (left) and Curium (right) isotope particles in the fuel salt over the observed operational period.
Table 1.
The plutonium vector appearing in the reactor after long term operation compared to the Pu vector of the TRU used for loading.
Fig 8.
The reduced fuel cycle like it would be given using MSFR fed with SNF.
Pictures: left http://www.wikiwand.com/en/Spent_fuel_pool, credit DOE License: Public domain, middle: EVOL benchmark configuration, right: Gorleben storage hall, Origin: GNS Gesellschaft für Nuklear-Service mbH.
Fig 9.
The classical double strata fuel cycle like it is foreseen for the implementation of P&T on industrial scale, today.
Fig 10.
Overview on the major challenges for the development of a MSFR following [5].