Literatura académica sobre el tema "Deuterium-Tritium fueling"
Crea una cita precisa en los estilos APA, MLA, Chicago, Harvard y otros
Consulte las listas temáticas de artículos, libros, tesis, actas de conferencias y otras fuentes académicas sobre el tema "Deuterium-Tritium fueling".
Junto a cada fuente en la lista de referencias hay un botón "Agregar a la bibliografía". Pulsa este botón, y generaremos automáticamente la referencia bibliográfica para la obra elegida en el estilo de cita que necesites: APA, MLA, Harvard, Vancouver, Chicago, etc.
También puede descargar el texto completo de la publicación académica en formato pdf y leer en línea su resumen siempre que esté disponible en los metadatos.
Artículos de revistas sobre el tema "Deuterium-Tritium fueling"
Graber, V. y E. Schuster. "Nonlinear burn control in ITER using adaptive allocation of actuators with uncertain dynamics". Nuclear Fusion 62, n.º 2 (1 de febrero de 2022): 026016. http://dx.doi.org/10.1088/1741-4326/ac3cd8.
Texto completoKing, D. B., R. Sharma, C. D. Challis, A. Bleasdale, E. G. Delabie, D. Douai, D. Keeling et al. "Tritium neutral beam injection on JET: calibration and plasma measurements of stored energy". Nuclear Fusion 63, n.º 11 (12 de octubre de 2023): 112005. http://dx.doi.org/10.1088/1741-4326/acee97.
Texto completoTala, T., A. E. Järvinen, C. F. Maggi, P. Mantica, A. Mariani, A. Salmi, I. S. Carvalho et al. "Isotope mass scaling and transport comparison between JET Deuterium and Tritium L-mode plasmas". Nuclear Fusion 63, n.º 11 (12 de octubre de 2023): 112012. http://dx.doi.org/10.1088/1741-4326/acea94.
Texto completoMilitello Asp, E., G. Corrigan, P. da Silva Aresta Belo, L. Garzotti, D. M. Harting, F. Köchl, V. Parail et al. "JINTRAC integrated simulations of ITER scenarios including fuelling and divertor power flux control for H, He and DT plasmas". Nuclear Fusion 62, n.º 12 (21 de octubre de 2022): 126033. http://dx.doi.org/10.1088/1741-4326/ac90d4.
Texto completoWauters, T., D. Matveev, D. Douai, J. Banks, R. Buckingham, I. S. Carvalho, E. de la Cal et al. "Isotope removal experiment in JET-ILW in view of T-removal after the 2nd DT campaign at JET". Physica Scripta 97, n.º 4 (11 de marzo de 2022): 044001. http://dx.doi.org/10.1088/1402-4896/ac5856.
Texto completoChaban, Ryan A., Saskia Mordijck, Aaron Michael Rosenthal, Alessandro Bortolon, Jerry W. Hughes, M. Knölker, Florian M. Laggner et al. "The role of isotope mass on neutral fueling and density pedestal structure in the DIII-D tokamak". Nuclear Fusion, 22 de enero de 2024. http://dx.doi.org/10.1088/1741-4326/ad2113.
Texto completoGraber, Vincent y Eugenio Schuster. "Divertor-safe nonlinear burn control based on a SOLPS parameterized core-edge model for ITER". Nuclear Fusion, 30 de mayo de 2024. http://dx.doi.org/10.1088/1741-4326/ad521b.
Texto completoValovic, Martin, Spyridon Aleiferis, Peter Blatchford, Alexandru Boboc, Mathias Brix, Pedro Carvalho, Ivo Samuel Carvalho et al. "Fuelling of deuterium-tritium plasma by peripheral pellets in JET experiments". Nuclear Fusion, 24 de abril de 2024. http://dx.doi.org/10.1088/1741-4326/ad42b2.
Texto completoBaylor, Larry R., Alexandre Deur, Nicholas W. Eidietis, William W. Heidbrink, Gary L. Jackson, Jie Liu, Michael M. Lowry et al. "Polarized fusion and potential in situ tests of fuel polarization survival in a tokamak plasma". Nuclear Fusion, 13 de marzo de 2023. http://dx.doi.org/10.1088/1741-4326/acc3ae.
Texto completoTesis sobre el tema "Deuterium-Tritium fueling"
Geulin, Eléonore. "Contribution to the modeling of pellet injection : from the injector to ablation in the plasma". Electronic Thesis or Diss., Aix-Marseille, 2023. http://www.theses.fr/2023AIXM0066.
Texto completoThe preferred method of fueling fusion device is the use of D and/or T pellets injected into the plasma. They are currently used, but the results cannot be extrapolated to future larger reactors where the design of the injection system and the construction of scenarios will be mainly based on simulations. It is therefore important to fill in the gaps in the existing models from the manufacture of pellets to the deposition of material in the plasma. Two lacks of knowledge appear: the modeling of the pellet transport in the injection pipe and the validation of the ablation process. This work aims to fill these gaps and consists of 3 parts.- Describe the physics of material deposition, then the state of the art of the main results and finally the description of the pellet injection systems planned for the next machines.- Model the transport of the pellet in the injection pipe. The effects taken into account in the model are the weakening of the ice during rebounds, the increase in its temperature and its erosion. The model gives in particular the slowing down and the loss of mass of the pellet during the journey, as well as the stored elastic energy linked to its integrity on leaving the tube.- Contribute to the validation of the HPI2 ablation code, by comparing its predictions to data measured in ablation clouds. The method used is a calculation of synthetic data sets from simulations and comparing them to measurements. This method made it possible to validate the assumptions and approximations of the ablation model
Actas de conferencias sobre el tema "Deuterium-Tritium fueling"
Couso, Daniel, Jose´ Fano, Felicidad Ferna´ndez, Elena Ferna´ndez, Julio A. Guirao, Jose´ L. Lastra, Victor J. Marti´nez, Javier Ordieres y Iva´n Va´zquez. "Development of Codes and Standards for ITER In-Vessel Components". En ASME 2011 Pressure Vessels and Piping Conference. ASMEDC, 2011. http://dx.doi.org/10.1115/pvp2011-57611.
Texto completo