Modeling of tritium release from ceramic breeders: Status and some implications for next-step devices

Federici, G.; Wu, C.H.; Raffray, A.R.; Billone, M.C.

doi:10.1016/0022-3115(92)90314-b

Cited by 38 publications

(10 citation statements)

References 72 publications

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“…Tritium production, via breeding reactions ( 2) and ( 3), in liquid and 50 ceramic lithium-based breeder materials, and tritium extraction have been demonstrated through capsule irradiation in fission reactors [221][222][223]. In practice only a fraction of neutrons produced can be used to breed tritium.…”

Section: Dt Neutron Effects and Tritium Self-sufficiencymentioning

confidence: 99%

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: 99%

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

et al. 2001

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“…Federici et al reported the estimation of the tritium recovery rate and the tritium inventory in tritium breeder under the ITER pulsed operation with their developed calculation code. 26) However, the in-situ tritium recovery experiments simulating the ITER pulsed operation was not carried out. The second experiment, therefore, was conducted in order to evaluate the effect of continuous pulsed operation on tritium recovery from Li 2 TiO 3 pebble bed.…”

Section: Irradiation Test With Pulse-operation Simulating Mockupmentioning

confidence: 99%

“…In Ref. 26), the tritium recovery rate shows a characteristic peak under the pulse operation due to the combined effect of the generation rate beginning and the temperature rising. From these results, it is considered that the buildup of the tritium inventory depends on the number of pulse operation cycles when (R/G) av was saturated.…”

Section: Irradiation Test With Pulse-operation Simulating Mockupmentioning

confidence: 99%

In-situTritium Recovery Experiments of Blanket In-pile Mockup with Li₂TiO₃Pebble Bed in Japan

Tsuchiya¹,

Nakamichi²,

Nagao³

et al. 2001

Journal of Nuclear Science and Technology

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Lithium titanate (Li 2 TiO 3 ) is one of the most attractive tritium breeders for breeding blanket in fusion reactor from view points of low tritium inventory, high chemical stability and so on. The data on the performance of a blanket mockup with pebble bed under neutron irradiation is needed for the design of breeding blanket. To obtain such data, two kinds of the blanket in-pile mockups with Li 2 TiO 3 pebble bed were developed and the in-situ tritium recovery experiments were carried out in the Japan Materials Testing Reactor (JMTR). In these studies, effects of various parameters, i.e., irradiation temperature, sweep gas flow rate, etc., on the tritium recovery behavior from Li 2 TiO 3 pebble bed were evaluated. It was found that the tritium recovery (R) to tritium generation (G) ratio (R/G) increased with increasing the temperature of Li 2 TiO 3 pebble bed and was saturated when the temperature of Li 2 TiO 3 pebble bed at the outside edge exceeded 300 • C. Additionally, the sweep gas flow rate in the range of 100 to 900 cm 3 /min affected very little the tritium recovery from Li 2 TiO 3 pebble bed. A good prospect for the design of breeding blankets using Li 2 TiO 3 pebble bed was obtained from these results of in-situ experiments.

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“…As the sweep gas, helium gas alone or helium gas with a small amount of hydrogen gas will be employed. Although some researches on hydrogen isotope behaviors for the Li 2 TiO 3 have been carried out so far [4][5][6][7], the effects of the sweep gas on the tritium removal and the tritium recovery ratio by the sweep gas is still unclear. Thus, they have to be clarified to improve the tritium recovery ratio.…”

Section: Introductionmentioning

confidence: 98%

Effects of hydrogen mixture into helium gas on deuterium removal from lithium titanate

Tsuchiya

Hino

Yamauchi

et al. 2013

Fusion Engineering and Design

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Modeling of tritium release from ceramic breeders: Status and some implications for next-step devices

Cited by 38 publications

References 72 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

In-situTritium Recovery Experiments of Blanket In-pile Mockup with Li₂TiO₃Pebble Bed in Japan

Effects of hydrogen mixture into helium gas on deuterium removal from lithium titanate

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Modeling of tritium release from ceramic breeders: Status and some implications for next-step devices

Cited by 38 publications

References 72 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

In-situTritium Recovery Experiments of Blanket In-pile Mockup with Li2TiO3Pebble Bed in Japan

Effects of hydrogen mixture into helium gas on deuterium removal from lithium titanate

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In-situTritium Recovery Experiments of Blanket In-pile Mockup with Li₂TiO₃Pebble Bed in Japan