Cost Assessment of a Tokamak Fusion Reactor with an Inventive Method for Optimum Build Determination
An inventive method was applied to determine the minimum major radius, <i>R</i><sub>0</sub>, and the optimum build of a tokamak fusion reactor that simultaneously meets all physics, engineering, and neutronics constraints. With a simple cost model, tokamak systems analyses we...
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MDPI AG
2021-10-01
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| Series: | Energies |
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| Online Access: | https://www.mdpi.com/1996-1073/14/20/6817 |
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| author | Gahyung Jo Jae-Min Kwon Ara Cho Hyun-Kyung Chung Bong-Guen Hong |
| author_facet | Gahyung Jo Jae-Min Kwon Ara Cho Hyun-Kyung Chung Bong-Guen Hong |
| author_sort | Gahyung Jo |
| collection | DOAJ |
| description | An inventive method was applied to determine the minimum major radius, <i>R</i><sub>0</sub>, and the optimum build of a tokamak fusion reactor that simultaneously meets all physics, engineering, and neutronics constraints. With a simple cost model, tokamak systems analyses were carried out over ranges of system parameters to find an optimum build of a tokamak fusion reactor at minimum cost. The impact of a wide range of physics parameters and advanced engineering elements on costs were also addressed. When a central solenoid was used to ramp up a plasma current, design solutions with a cost of electricity (COE) between 109 and 140 mills/kWh, direct capital cost between 5000 and 6000 M/USD, and net electric power, <i>P<sub>e</sub></i> between 1000 and 1600 MW could be found with a minimum <i>R</i><sub>0</sub> between 6.0 and 7.0 m, and fusion power, <i>P<sub>fusion</sub></i> between 2000 and 2800 MW. When the plasma current was driven by a non-inductive external system, the system size and costs could be reduced further; a COE between 98 and 130 mills/kWh, direct capital cost between 4000 and 5000 M$, and <i>P<sub>e</sub></i> between 1000 and 1420 MW could be found with a minimum <i>R</i><sub>0</sub> between 5.1 and 6.7 m, and <i>P<sub>fusion</sub></i> between 2000 and 2650 MW. |
| first_indexed | 2024-03-10T06:35:07Z |
| format | Article |
| id | doaj.art-d9688bdbb66f49208c66f5522bb76488 |
| institution | Directory Open Access Journal |
| issn | 1996-1073 |
| language | English |
| last_indexed | 2024-03-10T06:35:07Z |
| publishDate | 2021-10-01 |
| publisher | MDPI AG |
| record_format | Article |
| series | Energies |
| spelling | doaj.art-d9688bdbb66f49208c66f5522bb764882023-11-22T18:09:16ZengMDPI AGEnergies1996-10732021-10-011420681710.3390/en14206817Cost Assessment of a Tokamak Fusion Reactor with an Inventive Method for Optimum Build DeterminationGahyung Jo0Jae-Min Kwon1Ara Cho2Hyun-Kyung Chung3Bong-Guen Hong4Korea Institute of Fusion Energy, Daejeon 34133, KoreaKorea Institute of Fusion Energy, Daejeon 34133, KoreaKorea Institute of Fusion Energy, Daejeon 34133, KoreaKorea Institute of Fusion Energy, Daejeon 34133, KoreaQuantum System Engineering, Jeonbuk National University, Jeonju 54896, KoreaAn inventive method was applied to determine the minimum major radius, <i>R</i><sub>0</sub>, and the optimum build of a tokamak fusion reactor that simultaneously meets all physics, engineering, and neutronics constraints. With a simple cost model, tokamak systems analyses were carried out over ranges of system parameters to find an optimum build of a tokamak fusion reactor at minimum cost. The impact of a wide range of physics parameters and advanced engineering elements on costs were also addressed. When a central solenoid was used to ramp up a plasma current, design solutions with a cost of electricity (COE) between 109 and 140 mills/kWh, direct capital cost between 5000 and 6000 M/USD, and net electric power, <i>P<sub>e</sub></i> between 1000 and 1600 MW could be found with a minimum <i>R</i><sub>0</sub> between 6.0 and 7.0 m, and fusion power, <i>P<sub>fusion</sub></i> between 2000 and 2800 MW. When the plasma current was driven by a non-inductive external system, the system size and costs could be reduced further; a COE between 98 and 130 mills/kWh, direct capital cost between 4000 and 5000 M$, and <i>P<sub>e</sub></i> between 1000 and 1420 MW could be found with a minimum <i>R</i><sub>0</sub> between 5.1 and 6.7 m, and <i>P<sub>fusion</sub></i> between 2000 and 2650 MW.https://www.mdpi.com/1996-1073/14/20/6817coupled systems analysiscost assessmenttokamak fusion reactor |
| spellingShingle | Gahyung Jo Jae-Min Kwon Ara Cho Hyun-Kyung Chung Bong-Guen Hong Cost Assessment of a Tokamak Fusion Reactor with an Inventive Method for Optimum Build Determination Energies coupled systems analysis cost assessment tokamak fusion reactor |
| title | Cost Assessment of a Tokamak Fusion Reactor with an Inventive Method for Optimum Build Determination |
| title_full | Cost Assessment of a Tokamak Fusion Reactor with an Inventive Method for Optimum Build Determination |
| title_fullStr | Cost Assessment of a Tokamak Fusion Reactor with an Inventive Method for Optimum Build Determination |
| title_full_unstemmed | Cost Assessment of a Tokamak Fusion Reactor with an Inventive Method for Optimum Build Determination |
| title_short | Cost Assessment of a Tokamak Fusion Reactor with an Inventive Method for Optimum Build Determination |
| title_sort | cost assessment of a tokamak fusion reactor with an inventive method for optimum build determination |
| topic | coupled systems analysis cost assessment tokamak fusion reactor |
| url | https://www.mdpi.com/1996-1073/14/20/6817 |
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