Добірка наукової літератури з теми "Deuterium-Tritium fueling"
Оформте джерело за APA, MLA, Chicago, Harvard та іншими стилями
Ознайомтеся зі списками актуальних статей, книг, дисертацій, тез та інших наукових джерел на тему "Deuterium-Tritium fueling".
Біля кожної праці в переліку літератури доступна кнопка «Додати до бібліографії». Скористайтеся нею – і ми автоматично оформимо бібліографічне посилання на обрану працю в потрібному вам стилі цитування: APA, MLA, «Гарвард», «Чикаго», «Ванкувер» тощо.
Також ви можете завантажити повний текст наукової публікації у форматі «.pdf» та прочитати онлайн анотацію до роботи, якщо відповідні параметри наявні в метаданих.
Статті в журналах з теми "Deuterium-Tritium fueling":
Graber, V., and E. Schuster. "Nonlinear burn control in ITER using adaptive allocation of actuators with uncertain dynamics." Nuclear Fusion 62, no. 2 (February 1, 2022): 026016. http://dx.doi.org/10.1088/1741-4326/ac3cd8.
King, 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, no. 11 (October 12, 2023): 112005. http://dx.doi.org/10.1088/1741-4326/acee97.
Tala, 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, no. 11 (October 12, 2023): 112012. http://dx.doi.org/10.1088/1741-4326/acea94.
Militello 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, no. 12 (October 21, 2022): 126033. http://dx.doi.org/10.1088/1741-4326/ac90d4.
Wauters, 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, no. 4 (March 11, 2022): 044001. http://dx.doi.org/10.1088/1402-4896/ac5856.
Chaban, 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, January 22, 2024. http://dx.doi.org/10.1088/1741-4326/ad2113.
Graber, Vincent, and Eugenio Schuster. "Divertor-safe nonlinear burn control based on a SOLPS parameterized core-edge model for ITER." Nuclear Fusion, May 30, 2024. http://dx.doi.org/10.1088/1741-4326/ad521b.
Valovic, 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, April 24, 2024. http://dx.doi.org/10.1088/1741-4326/ad42b2.
Baylor, 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, March 13, 2023. http://dx.doi.org/10.1088/1741-4326/acc3ae.
Дисертації з теми "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.
The 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
Тези доповідей конференцій з теми "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, and Iva´n Va´zquez. "Development of Codes and Standards for ITER In-Vessel Components." In ASME 2011 Pressure Vessels and Piping Conference. ASMEDC, 2011. http://dx.doi.org/10.1115/pvp2011-57611.