Current Progress of Tritium Fuel Cycle Technology for CFETR
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During plasma operation of ITER in the DT phase, tritium will be distributed in the different subsystems of the fuel cycle; tritium inventories within the systems are not constant, but vary as the gas moves through these systems during the burn and dwell periods. To evaluate the tritium content in each sub-system of the fuel cycle of ITER, a dynamic model for tritium inventory calculation was developed. The code reflects the design of each system in various degrees of detail; both the physical processes characteristics and in some cases the associated control systems are modeled. The amount of tritium needed for ITER operation has a direct impact on the tritium inventories within the fuel cycle subsystems. As ITER will function in pulses, the main characteristics that influence both the maximum value of tritium inventories in the systems and the rapid tritium recovery from the fuel cycle as necessary for refueling are discussed. Eventually the inventories in the Isotope Separation System (as the system with the highest tritium inventory) for short and long pulses and their dependence on the packing molar inventory are presented.
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The tritium balance in a D-T fusion power reactor to assure a self-sustainable tritium system is discussed in this paper, comparing the amount of tritium consumed in the fueling cycle including the plasma vessel with the amount of tritium generated in the blanket system. It is determined that recovering tritium from the redeposition layer is highly effective in achieving tritium balance. It is also known from this discussion that having a burning plasma with an overall burning efficiency >0.5% is needed to maintain tritium balance. A burning efficiency >3 to 4% is even better because the tritium balance increases. It is also known that a first-wall material having an overall trapping factor >0.005 or that having an overall permeation loss ratio >0.0001 is not desirable because the tritium loss at the plasma vessel becomes too large to maintain the tritium balance. This discussion also finds that a blanket system with an overall breeding ratio of [approximately]1.1 is desirable early in fusion development to maintain a short tritium doubling time.
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Within the tritium plant of ITER a total inventory of about 2–3 kg will be necessary to operate the machine in the DT phase. During plasma operation, tritium will be distributed in the different sub-systems of the fuel cycle. A tool for tritium inventory evaluation within each sub-system of the fuel cycle is important with respect to both the process of licensing ITER and also for operation. It is very likely that measurements of total tritium inventories may not be possible for all sub-systems; however, tritium accounting may be achieved by modelling its hold-up within each sub-system and by validating these models in real-time against the monitored flows and tritium streams between the sub-systems. To get reliable results, an accurate dynamic modelling of the tritium content in each sub-system is necessary. A dynamic model (TRIMO) for tritium inventory calculation reflecting the design of each fuel cycle sub-systems was developed.
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The way to estimate the tritium breeding ratio in a D-T fusion power reactor to assure a self-sustainable tritium system is discussed in this paper comparing the required breeding ratio obtained from tritium balance in the fueling system of a power reactor including the plasma vessel with the attainable breeding ratio evaluated from efficiency in neutron usage and recovery efficiency of bred tritium in the blanket system. It is certified that recovery of tritium from the re-deposition layer together with suppression of the permeation loss through first wall and reduction of the total tritium inventory are effective to ease the tritium balance. It is not preferable to have the burning plasma of which overall burning efficiency is less than 0.5% from the viewpoint of tritium balance of a power reactor.
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Abstract The realization of tritium self-sufficiency has become an important step to the study of tritium cycle for fusion reactor. To realize tritium self-sufficiency of tritium cycle system of fusion reactor, a typical tritium cycle model of magnetically confined fusion reactor is established on the basis of CFETR in this paper. Tritium cycle model and tritium self-sufficiency are also studied. Based on the mean residence time method, the mass balance equations of the model are developed. Considering the tritium retention of the feeding system and plasma, the specific scheme of the model for calculating the minimum initial startup tritium inventory and the minimum tritium breeding ratio required for tritium self-sufficiency is given. The tritium inventory and the tritium treatment capacity requirements of each subsystem are obtained. In addition, the tritium inventory is also obtained through Simulink modeling and analysis. This is also a method to solve the problem, which can be used as a reference for the modeling and analysis of fusion reactor.
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