ASTRA: Difference between revisions

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Presently, the code is used for transport simulations of both [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be solved to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined. In this case, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220 dedicated subroutines] can be added to update at will the metric coefficients depending on the plasma currents. Moreover, despite the one-dimensional nature of the transport equations, appropriate handling of the integration space permits also making calculations that include magnetic islands or ergodic plasma regions<ref>D. López-Bruna, B. Momo, I. Predebon, A. López-Fraguas, F. Auriemma, Y. Suzuki, and R. Lorenzini, “Flux-surface averaged radial transport in toroidal plasmas with magnetic islands,” Nuclear Fusion, vol. 58, no. 10, p. 106031, 2018. [http://stacks.iop.org/0029-5515/58/i=10/a=106031]</ref>.

Presently, the code is used for transport simulations of both [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be solved to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined. In this case, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220 dedicated subroutines] can be added to update at will the metric coefficients depending on the plasma currents. Moreover, despite the one-dimensional nature of the transport equations, appropriate handling of the integration space permits also making calculations that include magnetic islands or ergodic plasma regions<ref>D. López-Bruna, B. Momo, I. Predebon, A. López-Fraguas, F. Auriemma, Y. Suzuki, and R. Lorenzini, “Flux-surface averaged radial transport in toroidal plasmas with [[Magnetic island|magnetic islands]],” Nuclear Fusion, vol. 58, no. 10, p. 106031, 2018. [http://stacks.iop.org/0029-5515/58/i=10/a=106031]</ref>.

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As an extension of the geometrical possibilities in ASTRA, plasma regions occupied by magnetic islands or ergodic regions (limited by flux surfaces) can be treated as well in the transport models<ref>D. López-Bruna, B. Momo, and Y. Zhang, “One-dimensional treatment of the effect of small magnetic islands on transport in the TJ-II stellarator,” Informe Técnico Ciemat 1402, CIEMAT, Madrid, May 2017</ref>.

As an extension of the geometrical possibilities in ASTRA, plasma regions occupied by [[Magnetic island|magnetic islands]] or ergodic regions (limited by flux surfaces) can be treated as well in the transport models<ref>D. López-Bruna, B. Momo, and Y. Zhang, “One-dimensional treatment of the effect of small magnetic islands on transport in the TJ-II stellarator,” Informe Técnico Ciemat 1402, CIEMAT, Madrid, May 2017</ref>.

Demanding calculations are conveniently done through system calls from the ASTRA subroutines. One such possible extensions of the ASTRA is the coupling of the calculations to the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and ~~Fafner~~ to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources; or the coupling to ray-tracing calculations, including the access to distributed resources<ref>D. López-Bruna, J. M. Reynolds, A. Cappa, J. Martinell, J. García, and C. Gutiérrez-Tapia, “Programas periféricos de ASTRA para el TJ-II,” Informe Técnico Ciemat 1201, CIEMAT, March 2010, [https://documenta.ciemat.es/bitstream/123456789/114/1/40921_IC1201.pdf]</ref>.

Demanding calculations are conveniently done through system calls from the ASTRA subroutines. One such possible extensions of the ASTRA is the coupling of the calculations to the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and [[FAFNER|FAFNER]] to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources; or the coupling to ray-tracing calculations, including the access to distributed resources<ref>D. López-Bruna, J. M. Reynolds, A. Cappa, J. Martinell, J. García, and C. Gutiérrez-Tapia, “Programas periféricos de ASTRA para el TJ-II,” Informe Técnico Ciemat 1201, CIEMAT, March 2010, [https://documenta.ciemat.es/bitstream/123456789/114/1/40921_IC1201.pdf]</ref>.

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-Presently, the code is used for transport simulations of both [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be solved to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined. In this case, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220 dedicated subroutines] can be added to update at will the metric coefficients depending on the plasma currents. Moreover, despite the one-dimensional nature of the transport equations, appropriate handling of the integration space permits also making calculations that include magnetic islands or ergodic plasma regions<ref>D. López-Bruna, B. Momo, I. Predebon, A. López-Fraguas, F. Auriemma, Y. Suzuki, and R. Lorenzini, “Flux-surface averaged radial transport in toroidal plasmas with magnetic islands,” Nuclear Fusion, vol. 58, no. 10, p. 106031, 2018. [http://stacks.iop.org/0029-5515/58/i=10/a=106031]</ref>.
+Presently, the code is used for transport simulations of both [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be solved to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined. In this case, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220 dedicated subroutines] can be added to update at will the metric coefficients depending on the plasma currents. Moreover, despite the one-dimensional nature of the transport equations, appropriate handling of the integration space permits also making calculations that include magnetic islands or ergodic plasma regions<ref>D. López-Bruna, B. Momo, I. Predebon, A. López-Fraguas, F. Auriemma, Y. Suzuki, and R. Lorenzini, “Flux-surface averaged radial transport in toroidal plasmas with [[Magnetic island|magnetic islands]],” Nuclear Fusion, vol. 58, no. 10, p. 106031, 2018. [http://stacks.iop.org/0029-5515/58/i=10/a=106031]</ref>.
@@ Line 18: / Line 18: @@
-As an extension of the geometrical possibilities in ASTRA, plasma regions occupied by magnetic islands or ergodic regions (limited by flux surfaces) can be treated as well in the transport models<ref>D. López-Bruna, B. Momo, and Y. Zhang, “One-dimensional treatment of the effect of small magnetic islands on transport in the TJ-II stellarator,” Informe Técnico Ciemat 1402, CIEMAT, Madrid, May 2017</ref>.
+As an extension of the geometrical possibilities in ASTRA, plasma regions occupied by [[Magnetic island|magnetic islands]] or ergodic regions (limited by flux surfaces) can be treated as well in the transport models<ref>D. López-Bruna, B. Momo, and Y. Zhang, “One-dimensional treatment of the effect of small magnetic islands on transport in the TJ-II stellarator,” Informe Técnico Ciemat 1402, CIEMAT, Madrid, May 2017</ref>.
-Demanding calculations are conveniently done through system calls from the ASTRA subroutines.  One such possible extensions of the ASTRA is the coupling of the calculations to the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and Fafner to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources; or the coupling to ray-tracing calculations, including the access to distributed resources<ref>D. López-Bruna, J. M. Reynolds, A. Cappa, J. Martinell, J. García, and C. Gutiérrez-Tapia, “Programas periféricos de ASTRA para el TJ-II,” Informe Técnico Ciemat 1201, CIEMAT, March 2010, [https://documenta.ciemat.es/bitstream/123456789/114/1/40921_IC1201.pdf]</ref>.
+Demanding calculations are conveniently done through system calls from the ASTRA subroutines.  One such possible extensions of the ASTRA is the coupling of the calculations to the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and [[FAFNER|FAFNER]] to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources; or the coupling to ray-tracing calculations, including the access to distributed resources<ref>D. López-Bruna, J. M. Reynolds, A. Cappa, J. Martinell, J. García, and C. Gutiérrez-Tapia, “Programas periféricos de ASTRA para el TJ-II,” Informe Técnico Ciemat 1201, CIEMAT, March 2010, [https://documenta.ciemat.es/bitstream/123456789/114/1/40921_IC1201.pdf]</ref>.