Nuclear Fusion最新文献_第10页

Comprehensive new insights on the potential use of SiC as plasma-facing materials in future fusion reactors 关于未来聚变反应堆中可能使用的面向等离子体的碳化硅材料的全面新见解

IF 3.3 1区物理与天体物理

Nuclear Fusion Pub Date : 2024-06-26 DOI: 10.1088/1741-4326/ad58f5

T. Sizyuk, J.N. Brooks, T. Abrams and A. Hassanein

{"title":"Comprehensive new insights on the potential use of SiC as plasma-facing materials in future fusion reactors","authors":"T. Sizyuk, J.N. Brooks, T. Abrams and A. Hassanein","doi":"10.1088/1741-4326/ad58f5","DOIUrl":"https://doi.org/10.1088/1741-4326/ad58f5","url":null,"abstract":"The performance of silicon carbide as an alternative plasma facing material (PFM) was studied at various irradiation conditions relevant to ion energies and fluxes of a fusion reactor. This analysis involves detailed modeling of subsurface plasma/material interactions, sputtered particle transport above the surface and redeposition, and related changes in material composition and microstructure induced by steady-state and Edge Localized Mode ion fluxes. Transition of a crystalline SiC surface to semi-crystalline and amorphous phases was analyzed based on advanced modeling of DIII-D tokamak experiments where SiC was irradiated in single- and multiple- L-mode and H-mode discharges. This analysis shows that displacement damage, particle deposition/redeposition, and D accumulation on the SiC divertor surface can lead to significant microstructural changes that result in enhanced sputtering erosion in comparison with the original crystalline material. However, the resulting total net erosion rate for a full-coverage, advanced tokamak, SiC coated divertor may well be acceptably low. Moreover, the C sputtering yield from the evolved SiC surface can be seven times lower than from a pure graphite surface; this would imply significantly reduced tritium co-deposition rates in a D-T tokamak reactor, compared with a pure carbon surface. It was also determined that chemical sputtering of both C and Si should not result in any noticeable effect on the net erosion, for attached plasma regimes. Our results thus show encouraging results overall for use of SiC as a PFM in tokamaks.","PeriodicalId":19379,"journal":{"name":"Nuclear Fusion","volume":"48 1","pages":""},"PeriodicalIF":3.3,"publicationDate":"2024-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141530675","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Gyrokinetic simulations of electrostatic microturbulence in ADITYA-U tokamak with argon impurity 带氩杂质的 ADITYA-U 托卡马克中静电微扰的陀螺动力学模拟

IF 3.3 1区物理与天体物理

Nuclear Fusion Pub Date : 2024-06-26 DOI: 10.1088/1741-4326/ad5a20

Tajinder Singh, Kajal Shah, Deepti Sharma, Joydeep Ghosh, Kumarpalsinh A. Jadeja, Rakesh L. Tanna, M.B. Chowdhuri, Zhihong Lin, Abhijit Sen, Sarveshwar Sharma and Animesh Kuley

{"title":"Gyrokinetic simulations of electrostatic microturbulence in ADITYA-U tokamak with argon impurity","authors":"Tajinder Singh, Kajal Shah, Deepti Sharma, Joydeep Ghosh, Kumarpalsinh A. Jadeja, Rakesh L. Tanna, M.B. Chowdhuri, Zhihong Lin, Abhijit Sen, Sarveshwar Sharma and Animesh Kuley","doi":"10.1088/1741-4326/ad5a20","DOIUrl":"https://doi.org/10.1088/1741-4326/ad5a20","url":null,"abstract":"The effect of impurity on the electrostatic microturbulence in ADITYA-U tokamak is assessed using global gyrokinetic simulations. The realistic geometry and experimental profiles of the ADITYA-U are used, before and after argon gas seeding, to perform the simulations. Before the impurity seeding, the simulations show the existence of the trapped electron mode (TEM) instability in three distinct regions on the radial-poloidal plane. The mode is identified by its linear eigenmode structure and its characteristic propagation in the electron diamagnetic direction. The simulations with Ar1+ impurity ions in the outer-core region show a significant reduction in the turbulence and transport due to a reduction in the linear instability drive, with respect to the case without impurity. A decrease in particle and heat transport in the outer-core region modifies the plasma density profile measured after the impurity seeding. It, thus, results in the stabilization of the TEM instability in the core region. Due to the reduced turbulence activity, the electron and ion temperatures in the central region increase by about 10%.","PeriodicalId":19379,"journal":{"name":"Nuclear Fusion","volume":"108 1","pages":""},"PeriodicalIF":3.3,"publicationDate":"2024-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141530676","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Stability and transport of gyrokinetic critical pedestals 陀螺仪临界基座的稳定性和传输

IF 3.3 1区物理与天体物理

Nuclear Fusion Pub Date : 2024-06-25 DOI: 10.1088/1741-4326/ad4d02

J.F. Parisi, A.O. Nelson, W. Guttenfelder, R. Gaur, J.W. Berkery, S.M. Kaye, K. Barada, C. Clauser, A. Diallo, D.R. Hatch, A. Kleiner, M. Lampert, T. Macwan and J.E. Menard

{"title":"Stability and transport of gyrokinetic critical pedestals","authors":"J.F. Parisi, A.O. Nelson, W. Guttenfelder, R. Gaur, J.W. Berkery, S.M. Kaye, K. Barada, C. Clauser, A. Diallo, D.R. Hatch, A. Kleiner, M. Lampert, T. Macwan and J.E. Menard","doi":"10.1088/1741-4326/ad4d02","DOIUrl":"https://doi.org/10.1088/1741-4326/ad4d02","url":null,"abstract":"A gyrokinetic threshold model for pedestal width–height scaling prediction is applied to multiple devices. A shaping and aspect ratio scan is performed on National Spherical Torus Experiment (NSTX) equilibria, finding for the wide-pedestal branch with pedestal width , aspect ratio A, elongation κ, triangularity δ, and normalized pedestal height . The width–transport scaling is found to vary significantly if the pedestal height is varied either with a fixed density or fixed temperature, showing how fueling and heating sources affect the pedestal density and temperature profiles for the kinetic-ballooning-mode (KBM) limited profiles. For an NSTX equilibrium, at fixed density, the wide branch is and at fixed temperature , where and are turbulent electron heat and particle fluxes and for an electron temperature and density . Pedestals close to the KBM limit are shown to have modified turbulent transport coefficients compared to the strongly driven KBMs. The role of flow shear is studied as a width–height scaling constraint and pedestal saturation mechanism for a standard and lithiated wide pedestal discharge. Finally, the stability, transport, and flow shear constraints are combined and examined for an NSTX experiment.","PeriodicalId":19379,"journal":{"name":"Nuclear Fusion","volume":"20 1","pages":""},"PeriodicalIF":3.3,"publicationDate":"2024-06-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141530678","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Nonlinear MHD modeling of soft β limits in W7-AS W7-AS 软 β 极限的非线性 MHD 建模

IF 3.3 1区物理与天体物理

Nuclear Fusion Pub Date : 2024-06-25 DOI: 10.1088/1741-4326/ad56a1

R. Ramasamy, K. Aleynikova, N. Nikulsin, F. Hindenlang, I. Holod, E. Strumberger, M. Hoelzl and the JOREK team

{"title":"Nonlinear MHD modeling of soft β limits in W7-AS","authors":"R. Ramasamy, K. Aleynikova, N. Nikulsin, F. Hindenlang, I. Holod, E. Strumberger, M. Hoelzl and the JOREK team","doi":"10.1088/1741-4326/ad56a1","DOIUrl":"https://doi.org/10.1088/1741-4326/ad56a1","url":null,"abstract":"An important question for the outlook of stellarator reactors is their robustness against pressure driven modes, and the underlying mechanism behind experimentally observed soft β limits. Towards building a robust answer to these questions, simulation studies are presented using a recently derived reduced nonlinear MHD model. First, the initial model implementation is extended to capture fluid compression by including the influence of parallel flows. Linear benchmarks of a (2, 1) tearing mode in W7-AS geometry, and interchange modes in a finite β, net-zero current carrying stellarator with low magnetic shear are then used to demonstrate the modeling capabilities. Finally, a validation study is conducted on experimental reconstructions of finite β W7-AS discharges. In agreement with past experimental analysis, it is shown that (i) the MHD activity is resistive, (ii) a soft β limit is observed, when the plasma resistivity approaches the estimated experimental value, and (iii) low n MHD activity is observed at intermediate β values, particularly a nonlinearly dominant (2, 1) mode. The MHD activity is mild, explaining the soft β limit, because the plasma volume remains separated into distinct sub-volumes in which field lines are ergodically confined. For the assumed transport parameters, the enhanced perpendicular transport along stochastic magnetic field lines can be overcome with the experimental heating power. The limitations in the current modeling are described, alongside an outlook for characterizing the quasi-steady state operational limit in W7-AS and other devices in more detail in future work.","PeriodicalId":19379,"journal":{"name":"Nuclear Fusion","volume":"36 1","pages":""},"PeriodicalIF":3.3,"publicationDate":"2024-06-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141530677","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

First results of laser-induced desorption - quadrupole mass spectrometry (LID-QMS) at JET 激光诱导解吸-四极杆质谱（LID-QMS）在 JET 的首批成果

IF 3.3 1区物理与天体物理

Nuclear Fusion Pub Date : 2024-06-24 DOI: 10.1088/1741-4326/ad52a5

M. Zlobinski, G. Sergienko, I. Jepu, C. Rowley, A. Widdowson, R. Ellis, D. Kos, I. Coffey, M. Fortune, D. Kinna, M. Beldishevski, A. Krimmer, H.T. Lambertz, A. Terra, A. Huber, S. Brezinsek, T. Dittmar, M. Flebbe, R. Yi, R. Rayaprolu, J. Figueiredo, P. Blatchford, S. Silburn, E. Tsitrone, E. Joffrin, K. Krieger, Y. Corre, A. Hakola, J. Likonen, the Eurofusion Tokamak Exploitation Team and JET Contributors

{"title":"First results of laser-induced desorption - quadrupole mass spectrometry (LID-QMS) at JET","authors":"M. Zlobinski, G. Sergienko, I. Jepu, C. Rowley, A. Widdowson, R. Ellis, D. Kos, I. Coffey, M. Fortune, D. Kinna, M. Beldishevski, A. Krimmer, H.T. Lambertz, A. Terra, A. Huber, S. Brezinsek, T. Dittmar, M. Flebbe, R. Yi, R. Rayaprolu, J. Figueiredo, P. Blatchford, S. Silburn, E. Tsitrone, E. Joffrin, K. Krieger, Y. Corre, A. Hakola, J. Likonen, the Eurofusion Tokamak Exploitation Team and JET Contributors","doi":"10.1088/1741-4326/ad52a5","DOIUrl":"https://doi.org/10.1088/1741-4326/ad52a5","url":null,"abstract":"The paper reports the first demonstration of in situ laser-induced desorption — quadrupole mass spectrometry (LID-QMS) application on a large scale fusion device performed in summer 2023. LID-QMS allows direct measurements of the fuel inventory of plasma facing components without retrieving them from the fusion device. The diagnostic desorbs the retained gases by heating a 3 mm diameter spot on the wall using a 1 ms long laser pulse and detects them by QMS. Thus, it can measure the gas content at any wall position accessible to the laser. The successful LID-QMS application in laboratory scale and on medium size fusion devices has now been demonstrated on the larger scale and it is already foreseen as tritium monitor diagnostic in ITER. This in situ diagnostic gives direct access to retention physics on a short timescale instead of campaign-integrated measurements and can assess the space-resolvedefficacy of detritation methods. LID-QMS can be applied on many materials: on Be deposits like in JET, B deposits like in TEXTOR, C based materials or on bulk-W.","PeriodicalId":19379,"journal":{"name":"Nuclear Fusion","volume":"35 1","pages":""},"PeriodicalIF":3.3,"publicationDate":"2024-06-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141530814","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Runaway electron dynamics in ITER disruptions with shattered pellet injections 热核聚变实验堆破碎颗粒注入扰动中的失控电子动力学

IF 3.3 1区物理与天体物理

Nuclear Fusion Pub Date : 2024-06-24 DOI: 10.1088/1741-4326/ad54d7

O. Vallhagen, L. Hanebring, F.J. Artola, M. Lehnen, E. Nardon, T. Fülöp, M. Hoppe, S.L. Newton and I. Pusztai

{"title":"Runaway electron dynamics in ITER disruptions with shattered pellet injections","authors":"O. Vallhagen, L. Hanebring, F.J. Artola, M. Lehnen, E. Nardon, T. Fülöp, M. Hoppe, S.L. Newton and I. Pusztai","doi":"10.1088/1741-4326/ad54d7","DOIUrl":"https://doi.org/10.1088/1741-4326/ad54d7","url":null,"abstract":"This study systematically explores the parameter space of disruption mitigation through shattered pellet injection in ITER with a focus on runaway electron (RE) dynamics, using the disruption modeling tool Dream. The physics fidelity is considerably increased compared to previous studies, by e.g. using realistic magnetic geometry, resistive wall configuration, thermal quench onset criteria, as well as including additional effects, such as ion transport and enhanced RE transport during the thermal quench. The work aims to provide a fairly comprehensive coverage of experimentally feasible scenarios, considering plasmas representative of both non-activated and high-performance DT operation, different thermal quench onset criteria and transport levels, a wide range of hydrogen and neon quantities injected in one or two stages, and pellets with various characteristic shard sizes. Using a staggered injection scheme, with a pure hydrogen injection preceding a mixed hydrogen-neon injection, we find injection parameters leading to acceptable RE currents in all investigated discharges without activated runaway sources. Dividing the injection into two stages is found to significantly enhance the assimilation and minimize RE generation due to the hot-tail mechanism. However, while a staggered injection outperforms a single stage injection also in cases with radioactive RE sources, no cases with acceptable RE currents are found for a DT-plasma with a plasma current.","PeriodicalId":19379,"journal":{"name":"Nuclear Fusion","volume":"24 1","pages":""},"PeriodicalIF":3.3,"publicationDate":"2024-06-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141530679","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Observation of a stationary double transport barrier in KSTAR 在 KSTAR 中观测到静止的双重传输障碍

IF 3.3 1区物理与天体物理

Nuclear Fusion Pub Date : 2024-06-23 DOI: 10.1088/1741-4326/ad521a

M.W. Lee, S.-H. Hahn, D. Kim, J. Kang, W.H. Ko, J. Jang, W. Lee and C. Sung

{"title":"Observation of a stationary double transport barrier in KSTAR","authors":"M.W. Lee, S.-H. Hahn, D. Kim, J. Kang, W.H. Ko, J. Jang, W. Lee and C. Sung","doi":"10.1088/1741-4326/ad521a","DOIUrl":"https://doi.org/10.1088/1741-4326/ad521a","url":null,"abstract":"We have observed a stationary high confinement regime with a double transport barrier (DTB), including both internal and edge transport barriers (ITB and ETB) but without edge-localized modes (ELMs), in KSTAR. The ELM-free DTB phase has high thermal confinement comparable to typical H-mode operation in KSTAR. We investigated the characteristics of the DTB phase through various analyses. Transport analysis shows a reduction of ion heat diffusivity to near neoclassical level after the transition from the ELMy H-mode phase to the DTB phase. This result supports the formation of an ion ITB during the DTB phase. Furthermore, we observed that the DTB phase had an edge thermal transport barrier in the ion temperature profile, comparable to that of the H-mode, without a particle transport barrier at the edge. Peeling-ballooning stability analysis indicates that a lower pressure gradient due to density decrease in the DTB phase is mainly responsible for the ELM-free operation. Linear gyrokinetic analysis shows that the real frequency of the most unstable mode in the core region ( = 0.32–0.47) is in the ion diamagnetic direction at both H-mode and DTB phases. At the DTB phase, the linear growth rate inside the ITB is reduced by 50% compared to the ITB foot, while the reduction is not shown at the H-mode phase. Further investigation including nonlinear effects will be needed to better understand the unique operation mode, which can contribute to applying the physical mechanism to fusion reactors in the future.","PeriodicalId":19379,"journal":{"name":"Nuclear Fusion","volume":"32 1","pages":""},"PeriodicalIF":3.3,"publicationDate":"2024-06-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141530815","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Studies of the outer-off-midplane lower hybrid wave launch scenario for plasma start-up on the TST-2 spherical tokamak 研究用于 TST-2 球形托卡马克等离子体启动的外偏中平面下混合波发射方案

IF 3.3 1区物理与天体物理

Nuclear Fusion Pub Date : 2024-06-19 DOI: 10.1088/1741-4326/ad52a9

N. Tsujii, A. Ejiri, Y. Ko, Y. Peng, K. Iwasaki, Y. Lin, K. Shinohara, O. Watanabe, S. Jang, T. Hidano, Y. Shirasawa, Y. Tian, F. Adachi and C.P. Moeller

{"title":"Studies of the outer-off-midplane lower hybrid wave launch scenario for plasma start-up on the TST-2 spherical tokamak","authors":"N. Tsujii, A. Ejiri, Y. Ko, Y. Peng, K. Iwasaki, Y. Lin, K. Shinohara, O. Watanabe, S. Jang, T. Hidano, Y. Shirasawa, Y. Tian, F. Adachi and C.P. Moeller","doi":"10.1088/1741-4326/ad52a9","DOIUrl":"https://doi.org/10.1088/1741-4326/ad52a9","url":null,"abstract":"Establishment of an efficient central solenoid (CS) free tokamak plasma start-up method may lead to an economical fusion reactor. CS-free start-up using lower hybrid (LH) waves has been studied on the TST-2 spherical tokamak. Plasma current of about a quarter of CS-driven discharges has been obtained fully non-inductively using the outer-midplane and top LH launchers. Recently, an outer-off-midplane LH launcher was developed to achieve higher plasma current by optimizing for core absorption and minimal fast electron losses. Using the (outer-)off-midplane launcher, fully non-inductive plasma current start-up up to about 8 kA was achieved. Coupled ray-tracing and Fokker–Planck simulation was performed on equilibria reconstructed with an extended MHD model. It was found that the experimentally observed plasma current was in reasonable agreement with the numerical simulation. The simulation predicted appreciable orbit losses for the off-midplane launcher driven discharge at the present parameters, which was consistent with the experimentally observed x-ray radiation characteristics. The simulation showed that the current density was saturated for the present off-midplane launcher discharges and higher density and higher LH power was necessary to achieve higher plasma current.","PeriodicalId":19379,"journal":{"name":"Nuclear Fusion","volume":"66 1","pages":""},"PeriodicalIF":3.3,"publicationDate":"2024-06-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141530816","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Turbulent particle pinch in gyrokinetic flux-driven ITG/TEM turbulence 陀螺动力通量驱动的 ITG/TEM 湍流中的湍流粒子挤压

IF 3.3 1区物理与天体物理

Nuclear Fusion Pub Date : 2024-06-17 DOI: 10.1088/1741-4326/ad52a4

Kenji Imadera, Yasuaki Kishimoto and Akihiro Ishizawa

引用次数: 0

Divertor-safe nonlinear burn control based on a SOLPS parameterized core-edge model for ITER 基于 SOLPS 参数化热核实验堆堆芯边缘模型的岔道安全非线性燃烧控制

IF 3.3 1区物理与天体物理

Nuclear Fusion Pub Date : 2024-06-17 DOI: 10.1088/1741-4326/ad521b

Vincent Graber and Eugenio Schuster

{"title":"Divertor-safe nonlinear burn control based on a SOLPS parameterized core-edge model for ITER","authors":"Vincent Graber and Eugenio Schuster","doi":"10.1088/1741-4326/ad521b","DOIUrl":"https://doi.org/10.1088/1741-4326/ad521b","url":null,"abstract":"For ITER operations, the range of desirable burning-plasma regimes with high fusion power output will be restricted by various operational constraints. These constraints include the saturation of ITER’s various heating and fueling actuators such as the neutral beam injectors, the ion and electron cyclotron heating systems, the gas puffing system, and the deuterium–tritium pellet injectors. In addition to these actuator constraints, the H-mode power threshold, divertor detachment, and the heat load on the divertor targets may apply limitations to ITER’s operational space. In this work, Plasma Operation Contour (POPCON) plots that map the aforementioned constraints to the temperature-density space are used to investigate which constraints are most limiting towards accessing regimes with high fusion power output. The presented POPCON plots are based on a control-oriented core-edge model that couples the nonlinear density and energy response models for the core-plasma region with SOLPS4.3 parameterizations for conditions in the edge-plasma regions (scrape-off-layer and divertor). Using this control-oriented core-edge model, a nonlinear burn controller, which aims to regulate the plasma temperature and density in the core-plasma region, is constructed in this work. This controller is augmented with an online optimization scheme that governs the control references such that the plasma can be guided towards regimes with high fusion powers while protecting the divertor targets from dangerously high heat loads. A closed-loop simulation study illustrates the capability of this burn control scheme.","PeriodicalId":19379,"journal":{"name":"Nuclear Fusion","volume":"24 1","pages":""},"PeriodicalIF":3.3,"publicationDate":"2024-06-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141530745","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":1,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0