Neutronic calculations of a thorium-based fusion–fission hybrid reactor blanket

Ma, Xubo; Chen, Y.X.; Wang, Y.; Zhang, P.Z.; Cao, Bo; Lu, Daogang; Cheng, Hao

doi:10.1016/j.fusengdes.2010.08.044

Cited by 9 publications

(7 citation statements)

References 5 publications

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“…However, they are highly fissionable in fusion reactors, multiplying the energy output of fusion plants to several folds. In that way, fusion reactors are predestinated to incinerate nuclear waste while producing simultaneously extra fission energy from the same fuel resource, reduce drastically the final disposal mass 13,33,47,51‐53 Fertile natural isotopes 232 Th and 238 U become fissile fuels under high energetic fusion neutron irradiation.…”

Section: Resultsmentioning

confidence: 99%

“…Fertile natural isotopes 232 Th and 238 U become fissile fuels under high energetic fusion neutron irradiation. This increases the world's nuclear energy resources by two orders of magnitude 53 Induced fission neutrons increase the tritium breeding rate of per fusion reactions, and also produce fissile fuels 233 U and 239 Pu for satellite fission reactors 5,22,51,52,54‐56 …”

Section: Resultsmentioning

confidence: 99%

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Study on the fusion reactor performance with different materials and nuclear waste actinides

Şahi̇n

Sahiner

et al. 2020

Int J Energy Res

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Summary In this study, both pure fusion blanket and fusion‐fission (hybrid) reactor blanket performance were investigated and discussed separately in two phases. In the first phase, a Monte Carlo radiation damage analysis has been performed for stainless steel (SS304, SS316, and oxide dispersion strengthened (ODS)), molybdenum, vanadium, and tungsten as the first wall (FW) materials, in combination with selected tritium breeders. The main technical parameters for fusion reactors, such as tritium breeding ratio, fusion energy multiplication factor (M), displacement per atom (DPA), and gas production (He, H) have been evaluated. All numerical calculations have been carried out in spherical geometry with MCNP6 code package using continuous energy cross‐sections from the ENDF/B‐VIII.0 library, except DPA calculations. Instead of the ENDF/B‐VIII.0 library, the 30‐group CLAW‐IV library was employed for DPA calculations. Structural material selection for the FW respect to radiation damage limits and reactor performance for energy production and tritium has been concluded. Conventional thermal reactors, such as light water reactors andCanada Deuterium Uranium (CANDU) reactors are producing substantial quantities of transuranic elements, which represent serious nuisance and permanent hazard potential. On the other hand, they become fissionable material under high energetic fusion neutron irradiation and multiply the fusion energy. In the second phase, the investigations are extended to the incineration of minor actinides (MA) in the fusion‐fission (hybrid) mode. The transmutation history of MA nuclear waste is included. MA are added into the first zone of the coolant in TRi‐structural ISOtropic particle TRISO particles with a volume fraction of 6%. The transformation scenario for all MA by SS 304 steel FW is practically the same as with the ODS FW.

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Section: Resultsmentioning

confidence: 99%

Section: Resultsmentioning

confidence: 99%

Study on the fusion reactor performance with different materials and nuclear waste actinides

Şahi̇n

Sahiner

et al. 2020

Int J Energy Res

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“…Hence, a 233 U breeder with a very small amount of fission when compared to a thermal reactor might be advantageous, and for this purpose fusion neutron sources might be a very good choice, since the bred fissile material can be used in a thermal reactor for the sole purpose of power generation, with very limited breeding (Moir, 1982). The use of fusion reactors as thorium-based breeders has been proposed in the past with promising results (Ş ahin and Yapıcı, 1999;Ma et al, 2010). In fact, a completely reprocessing-free (ReFree) nuclear fuel cycle with a fusion neutron source at its heart has been proposed (Kotschenreuther et al, 2012).…”

Section: Introductionmentioning

confidence: 99%

A 232Th closed fuel cycle utilizing both a thermal and hybrid nuclear systems

Perez-Gamboa

Nieto-Pérez

Mahajan

et al. 2015

Progress in Nuclear Energy

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“…Early work has investigated the possibility of production of 233 U in the fusion-fission reactor [1][2][3][4][5][6][7][8]. Considering the abundance of thorium, a thorium-based breeding blanket concept of fuel production is proposed.…”

Section: Introductionmentioning

confidence: 99%