Deuterium-Tritium Fuel Self-Sufficiency in Fusion Reactors

Abdou, Mohamed; Vold, Erik; Gung, C.; Youssef, M.Z.; Shin, Kyuchul

doi:10.13182/fst86-a24715

Cited by 124 publications

(38 citation statements)

References 11 publications

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“…As shown in Ref. [225], a factor of two increase in the tritium burn-fraction can have a significant effect on the tritium breeding ratio required for tritium self-sufficiency, reducing it from values of ≈1.15 to about 1.05.…”

Section: Dt Neutron Effects and Tritium Self-sufficiencymentioning

confidence: 85%

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

et al. 2001

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The major increase in discharge duration and plasma energy in a next step DT fusion reactor will give rise to important plasma-material effects that will critically influence its operation, safety and performance. Erosion will increase to a scale of several centimetres from being barely measurable at a micron scale in today's tokamaks. Tritium co-deposited with carbon will strongly affect the operation of machines with carbon plasma facing components. Controlling plasma-wall interactions is critical to achieving high performance in present day tokamaks, and this is likely to continue to be the case in the approach to practical fusion reactors. Recognition of the important consequences of these phenomena stimulated an internationally co-ordinated effort in the field of plasma-surface interactions supporting the Engineering Design Activities of the International Thermonuclear Experimental Reactor project (ITER), and significant progress has been made in better understanding these issues. The paper reviews the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next step fusion reactors. Two main topical groups of interaction are considered: (i) erosion/redeposition from plasma sputtering and disruptions, including dust and flake generation and (ii) tritium retention and removal. The use of modelling tools to interpret the experimental results and make projections for conditions expected in future devices is explained. Outstanding technical issues and specific recommendations on potential R&D avenues for their resolution are presented.

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Section: Dt Neutron Effects and Tritium Self-sufficiencymentioning

confidence: 85%

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

et al. 2001

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“…In the hybrid reactor system, the working liquid must be a lithium-containing medium to provide adequate tritium so that the plasma is self-sustaining and the fusion is a renewable energy source. the required TBR for a fission reactor conceptual design must be 1.1 [11][12][13][14][15]. TBR can be given as follows:…”

Section: Tritium Breedingmentioning

confidence: 99%

Three-dimensional Monte Carlo calculation of some nuclear parameters

Günay

Şeker

2017

EPJ Web Conf.

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Abstract. In this study, a fusion-fission hybrid reactor system was designed by using 9Cr2WVTa Ferritic steel structural material and the molten salt-heavy metal mixtures 99-95% Li 20 Sn 80 + 1-5% RG-Pu, 99-95% Li 20 Sn 80 + 1-5% RG-PuF 4 , and 99-95% Li 20 Sn 80 + 1-5% RG-PuO 2 , as fluids. The fluids were used in the liquid first wall, blanket and shield zones of a fusion-fission hybrid reactor system. Beryllium (Be) zone with the width of 3 cm was used for the neutron multiplication between the liquid first wall and blanket. This study analyzes the nuclear parameters such as tritium breeding ratio (TBR), energy multiplication factor (M), heat deposition rate, fission reaction rate in liquid first wall, blanket and shield zones and investigates effects of reactor grade Pu content in the designed system on these nuclear parameters. Threedimensional analyses were performed by using the Monte Carlo code MCNPX-2.7.0 and nuclear data library ENDF/B-VII.0.

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“…Presently, the only place in which tritium is artificially produced for ITER and other D-T fusion reactors is in CANDU reactor type with about 1.7 kg/year production rate [2]. One of the important characteristics of ITER is its tritium ''self-sufficiency'' [3][4][5][6][7]. In other words, tritium is produced in it, at least for its own consumption.…”

Section: Introductionmentioning

confidence: 99%

Tritium Breeding Ratio Calculation for ITER Tokamak Using Developed Helium Cooled Pebble Bed Blanket (HCPB)

Soltani

Habibi

2015

J Fusion Energ

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In this paper, neutronic calculations were performed to obtain tritium breeding ratio (TBR) for ITER device using developed helium cooled pebble (HCPB) blanket. The designed blanket module has the following combinations; natural lithium, Li 4 SiO 4 (20 %), beryllium moderator and neutron multiplier. To ensure tritium selfsufficiency, the calculated achievable TBR should be equal to or greater than the required TBR. Simulations have been performed by means of Monte Carlo MCNP-4C code using END/B-VII.1 data library. Results show that TBR of 1.14 is obtained for this new HCPB.

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Deuterium-Tritium Fuel Self-Sufficiency in Fusion Reactors

Cited by 124 publications

References 11 publications

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

Three-dimensional Monte Carlo calculation of some nuclear parameters

Tritium Breeding Ratio Calculation for ITER Tokamak Using Developed Helium Cooled Pebble Bed Blanket (HCPB)

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