Neutronics analysis of the power flattening and minor actinides burning in a thorium-based fusion–fission hybrid reactor blanket

Ma, Xuan; Chen, Y.X.; Quan, Guo; Wang, L.Z.; Lu, Daogang

doi:10.1016/j.fusengdes.2012.06.010

Cited by 8 publications

(2 citation statements)

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“…The concept of hybrid fusion-fission systems can be compared with an accelerator-driven (subcritical) system (ADS). The blanket of a hybrid fusion system could therefore contain the same fuel as an ADS: for example, the abundant element Th [52] or the longlived heavy isotopes present in the spent nuclear fuel (SNF) could be used as fuel (see, as examples, [39,41,42,47].…”

Section: Hybrid Fusion-fission Systemsmentioning

confidence: 99%

“…Notwithstanding, hybrid fusion fission systems have been already studied for some decades, in the most prominent laboratories and a large bibliography was produced . Obviously much more papers on this topic have been published in more recent years (just to give some examples up to the end of the previous decade, see [34][35][36][37][38][39][40][41][42][43][44][45][46][47][48].…”

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confidence: 99%

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Preliminary Assessment of the Transmutation Potentialities for an ITER-like FW Sector Loaded with MA

Scarfò

Caiffi

Chersola

et al. 2015

Glob. J. Energ. Technol. Res. Updat.

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The fusion-fission hybrid reactor is a promising technology that is likely to assume an increasingly important role in the global energy scene in the coming years. This kind of reactor can use both the nuclear fusion and fission processes to produce energy: neutrons from fusion reactions are used to sustain the fission of a sub-critical system. This method allows to have an intrinsically safe facility, with higher efficiency than a fusion reactor itself and with a harder neutron energy spectrum than a fission reactor, which could be suitable for nuclear waste transmutation. This paper, in particular, analyzes a type of hybrid reactor for the transmutation of Minor Actinides (MA). Nuclear waste, in the oxide form, is inserted as an element of the First Wall (FW) of an ITER-like fusion reactor. The aim is to demonstrate the feasibility of the transmutation of the MA characterized by higher long term radiotoxicity into shorter lived nuclides. The neutron transport in a detailed 3D geometrical model of the ITER reactor (B-lite) was performed by MCNP6 code, while the transmutation of the MA loaded in a single element of the FW was performed by SERPENT2 code. A pulsed ITER-like irradiation scenario was used. The analysis, which must be considered as a preliminary feasibility study, lead to very promising results, which could be further improved with a longer DEMO-like irradiation scenario and a larger number of MA loaded (“fission waste”) elements loaded in the FW.

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