Dynamics effects of tritium reduction on the energy gain of D-T fuel pellet using double cone ignition
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Roohalah Mirzaeian
and
Mahboobeh Shaghaghian
Abstract
In this paper a study of the behavior of Deuterium-Tritium (D-T) plasma nuclear fusion reaction in terms of variations of time and temperature and in the presence of deuterium-tritium sources using double cone ignition is presented. The aim is the determination of the optimum physical conditions with low tritium consumption rate for obtaining the total energy gain with a value of greater than 200.
Acknowledgement
The support provided by Islamic Azad University of Shiraz is grateful acknowledged.
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Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: None declared.
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Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
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Articles in the same Issue
- Frontmatter
- Application of the COCOSYS code in the safety evaluation of Czech nuclear power plants
- Improving of electric network feeding nuclear facility based on multiple types DGs placement
- Design and evaluation of ecological interface for Feedwater Deaerating Tank and Gas Stripper System based on cognitive work analysis
- Evaluation of different integrated burnable absorber materials in fuel assemblies of Bushehr WWER-1000 nuclear reactor
- Effective physical protection system design and implementation at a radiological facility: an integrated and risk management approach
- Determination of limiter design and material composition of MT-II spherical tokamak
- Dynamics effects of tritium reduction on the energy gain of D-T fuel pellet using double cone ignition
- Design of an unattended ore grading measurement system in a uranium mine
- Prediction of heat transfer characteristics in a microchannel with vortex generators by machine learning
- Prediction of nanofluid flows’ optimum velocity in finned tube-in-tube heat exchangers using artificial neural network
- Investigating the in-core 60Co production assembly for open pool type reactor
- Calendar of events
Articles in the same Issue
- Frontmatter
- Application of the COCOSYS code in the safety evaluation of Czech nuclear power plants
- Improving of electric network feeding nuclear facility based on multiple types DGs placement
- Design and evaluation of ecological interface for Feedwater Deaerating Tank and Gas Stripper System based on cognitive work analysis
- Evaluation of different integrated burnable absorber materials in fuel assemblies of Bushehr WWER-1000 nuclear reactor
- Effective physical protection system design and implementation at a radiological facility: an integrated and risk management approach
- Determination of limiter design and material composition of MT-II spherical tokamak
- Dynamics effects of tritium reduction on the energy gain of D-T fuel pellet using double cone ignition
- Design of an unattended ore grading measurement system in a uranium mine
- Prediction of heat transfer characteristics in a microchannel with vortex generators by machine learning
- Prediction of nanofluid flows’ optimum velocity in finned tube-in-tube heat exchangers using artificial neural network
- Investigating the in-core 60Co production assembly for open pool type reactor
- Calendar of events
