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Title: Orchestrating TRANSP Simulations for Interpretative and Predictive Tokamak Modeling with OMFIT

Abstract

TRANSP simulations are being used in the OMFIT work- flow manager to enable a machine independent means of experimental analysis, postdictive validation, and predictive time dependent simulations on the DIII-D, NSTX, JET and C-MOD tokamaks. The procedures for preparing the input data from plasma profile diagnostics and equilibrium reconstruction, as well as processing of the time-dependent heating and current drive sources and assumptions about the neutral recycling, vary across machines, but are streamlined by using a common workflow manager. Settings for TRANSP simulation fidelity are incorporated into the OMFIT framework, contrasting between-shot analysis, power balance, and fast-particle simulations. A previously established series of data consistency metrics are computed such as comparison of experimental vs. calculated neutron rate, equilibrium stored energy vs. total stored energy from profile and fast-ion pressure, and experimental vs. computed surface loop voltage. Discrepancies between data consistency metrics can indicate errors in input quantities such as electron density profile or Zeff, or indicate anomalous fast-particle transport. Measures to assess the sensitivity of the verification metrics to input quantities are provided by OMFIT, including scans of the input profiles and standardized post-processing visualizations. For predictive simulations, TRANSP uses GLF23 or TGLF to predict core plasma profiles, with usermore » defined boundary conditions in the outer region of the plasma. ITPA validation metrics are provided in post-processing to assess the transport model validity. By using OMFIT to orchestrate the steps for experimental data preparation, selection of operating mode, submission, post-processing and visualization, we have streamlined and standardized the usage of TRANSP.« less

Authors:
ORCiD logo [1];  [1];  [1];  [1];  [1];  [2];  [1];  [3];  [3];  [2];  [1];  [1];  [1]
  1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  2. General Atomics, San Diego, CA (United States)
  3. Culham Science Centre, Abingdon (United Kingdom). Culham Centre for Fusion Energy (CCFE), EURATOM/UKAEA Fusion Association
Publication Date:
Research Org.:
General Atomics, San Diego, CA (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
OSTI Identifier:
1424383
Grant/Contract Number:  
FC02-04ER54698; AC02-09CH11466
Resource Type:
Accepted Manuscript
Journal Name:
Fusion Science and Technology
Additional Journal Information:
Journal Volume: 73; Journal Issue: 2018; Related Information: Pages 1-15; Journal ID: ISSN 1536-1055
Publisher:
American Nuclear Society
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; TRANSP; integrated simulations; plasma transport

Citation Formats

Grierson, B. A., Yuan, X., Gorelenkova, M., Kaye, S., Logan, N. C., Meneghini, O., Haskey, S. R., Buchanan, J., Fitzgerald, M., Smith, S. P., Cui, L., Budny, R. V., and Poli, F. M. Orchestrating TRANSP Simulations for Interpretative and Predictive Tokamak Modeling with OMFIT. United States: N. p., 2018. Web. doi:10.1080/15361055.2017.1398585.
Grierson, B. A., Yuan, X., Gorelenkova, M., Kaye, S., Logan, N. C., Meneghini, O., Haskey, S. R., Buchanan, J., Fitzgerald, M., Smith, S. P., Cui, L., Budny, R. V., & Poli, F. M. Orchestrating TRANSP Simulations for Interpretative and Predictive Tokamak Modeling with OMFIT. United States. https://doi.org/10.1080/15361055.2017.1398585
Grierson, B. A., Yuan, X., Gorelenkova, M., Kaye, S., Logan, N. C., Meneghini, O., Haskey, S. R., Buchanan, J., Fitzgerald, M., Smith, S. P., Cui, L., Budny, R. V., and Poli, F. M. Wed . "Orchestrating TRANSP Simulations for Interpretative and Predictive Tokamak Modeling with OMFIT". United States. https://doi.org/10.1080/15361055.2017.1398585. https://www.osti.gov/servlets/purl/1424383.
@article{osti_1424383,
title = {Orchestrating TRANSP Simulations for Interpretative and Predictive Tokamak Modeling with OMFIT},
author = {Grierson, B. A. and Yuan, X. and Gorelenkova, M. and Kaye, S. and Logan, N. C. and Meneghini, O. and Haskey, S. R. and Buchanan, J. and Fitzgerald, M. and Smith, S. P. and Cui, L. and Budny, R. V. and Poli, F. M.},
abstractNote = {TRANSP simulations are being used in the OMFIT work- flow manager to enable a machine independent means of experimental analysis, postdictive validation, and predictive time dependent simulations on the DIII-D, NSTX, JET and C-MOD tokamaks. The procedures for preparing the input data from plasma profile diagnostics and equilibrium reconstruction, as well as processing of the time-dependent heating and current drive sources and assumptions about the neutral recycling, vary across machines, but are streamlined by using a common workflow manager. Settings for TRANSP simulation fidelity are incorporated into the OMFIT framework, contrasting between-shot analysis, power balance, and fast-particle simulations. A previously established series of data consistency metrics are computed such as comparison of experimental vs. calculated neutron rate, equilibrium stored energy vs. total stored energy from profile and fast-ion pressure, and experimental vs. computed surface loop voltage. Discrepancies between data consistency metrics can indicate errors in input quantities such as electron density profile or Zeff, or indicate anomalous fast-particle transport. Measures to assess the sensitivity of the verification metrics to input quantities are provided by OMFIT, including scans of the input profiles and standardized post-processing visualizations. For predictive simulations, TRANSP uses GLF23 or TGLF to predict core plasma profiles, with user defined boundary conditions in the outer region of the plasma. ITPA validation metrics are provided in post-processing to assess the transport model validity. By using OMFIT to orchestrate the steps for experimental data preparation, selection of operating mode, submission, post-processing and visualization, we have streamlined and standardized the usage of TRANSP.},
doi = {10.1080/15361055.2017.1398585},
journal = {Fusion Science and Technology},
number = 2018,
volume = 73,
place = {United States},
year = {Wed Feb 21 00:00:00 EST 2018},
month = {Wed Feb 21 00:00:00 EST 2018}
}

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Works referenced in this record:

Integrated modeling applications for tokamak experiments with OMFIT
journal, July 2015


Simultaneous measurement of q and Er profiles using the motional Stark effect in high-performance DIII-D plasmas (invited)
journal, January 1999

  • Rice, B. W.; Nilson, D. G.; Burrell, K. H.
  • Review of Scientific Instruments, Vol. 70, Issue 1
  • DOI: 10.1063/1.1149317

Predictive simulations of ITER including neutral beam driven toroidal rotation
journal, June 2008

  • Halpern, Federico D.; Kritz, Arnold H.; Bateman, Glenn
  • Physics of Plasmas, Vol. 15, Issue 6
  • DOI: 10.1063/1.2931037

Reconstruction of current profile parameters and plasma shapes in tokamaks
journal, November 1985


GLF23 Modeling of Turbulent Transport in DIII-D
journal, October 2005


Parallel electric resistivity in the TFTR tokamak
journal, August 1990

  • Zarnstorff, M. C.; McGuire, K.; Bell, M. G.
  • Physics of Fluids B: Plasma Physics, Vol. 2, Issue 8
  • DOI: 10.1063/1.859456

Magnetic topology, disruptions and electron heat transport
journal, January 1986


Statistical validation of predictive TRANSP simulations of baseline discharges in preparation for extrapolation to JET D–T
journal, May 2017


New techniques for calculating heat and particle source rates due to neutral beam injection in axisymmetric tokamaks
journal, September 1981


The first transport code simulations using the trapped gyro-Landau-fluid model
journal, May 2008

  • Kinsey, J. E.; Staebler, G. M.; Waltz, R. E.
  • Physics of Plasmas, Vol. 15, Issue 5
  • DOI: 10.1063/1.2889008

Fast-ion Dα measurements of the fast-ion distribution (invited)
journal, October 2010

  • Heidbrink, W. W.
  • Review of Scientific Instruments, Vol. 81, Issue 10
  • DOI: 10.1063/1.3478739

Numerical Transport Codes
journal, February 2012

  • Ongena, J. P. H. E.; Voitsekhovitch, I.; Evrard, M.
  • Fusion Science and Technology, Vol. 61, Issue 2T
  • DOI: 10.13182/FST12-A13505

Gyro-Landau fluid equations for trapped and passing particles
journal, October 2005

  • Staebler, G. M.; Kinsey, J. E.; Waltz, R. E.
  • Physics of Plasmas, Vol. 12, Issue 10
  • DOI: 10.1063/1.2044587

MHD Equilibrium Reconstruction in the DIII-D Tokamak
journal, October 2005

  • Lao, L. L.; John, H. E. St.; Peng, Q.
  • Fusion Science and Technology, Vol. 48, Issue 2
  • DOI: 10.13182/FST48-968

Quantification of the impact of large and small-scale instabilities on the fast-ion confinement in ASDEX Upgrade
journal, November 2014


The behaviour of fast ions in tokamak experiments
journal, April 1994


Integrated modelling of steady-state scenarios and heating and current drive mixes for ITER
journal, August 2011


Alpha heating in ITER L-mode and H-mode plasmas
journal, November 2011


Fusion power production in International Thermonuclear Experimental Reactor baseline H-mode scenarios
journal, April 2015

  • Rafiq, T.; Kritz, A. H.; Kessel, C. E.
  • Physics of Plasmas, Vol. 22, Issue 4
  • DOI: 10.1063/1.4917522

Off-axis neutral beam current drive for advanced scenario development in DIII-D
journal, May 2009


Improved Multi-Mode anomalous transport module for tokamak plasmas
journal, October 2013


Validation metrics for turbulent plasma transport
journal, June 2016


Bootstrap current and neoclassical transport in tokamaks of arbitrary collisionality and aspect ratio
journal, September 1997

  • Houlberg, W. A.; Shaing, K. C.; Hirshman, S. P.
  • Physics of Plasmas, Vol. 4, Issue 9
  • DOI: 10.1063/1.872465

Experimental and modeling uncertainties in the validation of lower hybrid current drive
journal, July 2016


Novel free-boundary equilibrium and transport solver with theory-based models and its validation against ASDEX Upgrade current ramp scenarios
journal, November 2013


Dependence of intrinsic torque and momentum confinement on normalized gyroradius and collisionality in the DIII-D tokamak
journal, April 2017

  • Chrystal, C.; Grierson, B. A.; Solomon, W. M.
  • Physics of Plasmas, Vol. 24, Issue 4
  • DOI: 10.1063/1.4978563

Simulations of deuterium-tritium experiments in TFTR
journal, March 1992


Integrated modeling of temperature profiles in L-mode tokamak discharges
journal, December 2014

  • Rafiq, T.; Kritz, A. H.; Tangri, V.
  • Physics of Plasmas, Vol. 21, Issue 12
  • DOI: 10.1063/1.4903464

The tokamak Monte Carlo fast ion module NUBEAM in the National Transport Code Collaboration library
journal, June 2004

  • Pankin, Alexei; McCune, Douglas; Andre, Robert
  • Computer Physics Communications, Vol. 159, Issue 3
  • DOI: 10.1016/j.cpc.2003.11.002

A gyro-Landau-fluid transport model
journal, July 1997

  • Waltz, R. E.; Staebler, G. M.; Dorland, W.
  • Physics of Plasmas, Vol. 4, Issue 7
  • DOI: 10.1063/1.872228

A theory-based transport model with comprehensive physics
journal, May 2007

  • Staebler, G. M.; Kinsey, J. E.; Waltz, R. E.
  • Physics of Plasmas, Vol. 14, Issue 5
  • DOI: 10.1063/1.2436852

Predictions of H-mode performance in ITER
journal, May 2008


The behaviour of fast ions in tokamak experiments
journal, February 1995


Numerical Transport Codes
journal, February 2010

  • Ongena, J. P. H. E.; Voitsekhovitch, I.; Evrard, M.
  • Fusion Science and Technology, Vol. 57, Issue 2T
  • DOI: 10.13182/fst10-a9429

Works referencing / citing this record:

Neutron Diagnostics for Tokamak Plasma: From a Plasma Diagnostician Perspective
journal, October 2018


Validation of nonlinear gyrokinetic transport models using turbulence measurements
journal, February 2019


Relative intensity calibration of the DIII-D charge-exchange recombination spectroscopy system using neutral beam injection into gas
journal, October 2018

  • Grierson, B. A.; Burrell, K. H.; Chrystal, C.
  • Review of Scientific Instruments, Vol. 89, Issue 10
  • DOI: 10.1063/1.5037333

Active spectroscopy measurements of the deuterium temperature, rotation, and density from the core to scrape off layer on the DIII-D tokamak (invited)
journal, October 2018

  • Haskey, S. R.; Grierson, B. A.; Stagner, L.
  • Review of Scientific Instruments, Vol. 89, Issue 10
  • DOI: 10.1063/1.5038349

Propagation of input parameter uncertainties in transport models
journal, October 2018

  • Vaezi, P.; Holland, C.; Grierson, B. A.
  • Physics of Plasmas, Vol. 25, Issue 10
  • DOI: 10.1063/1.5053906

Main-ion intrinsic toroidal rotation across the ITG/TEM boundary in DIII-D discharges during ohmic and electron cyclotron heating
journal, April 2019

  • Grierson, B. A.; Chrystal, C.; Haskey, S. R.
  • Physics of Plasmas, Vol. 26, Issue 4
  • DOI: 10.1063/1.5090505

Predict-first experiments and modeling of perturbative cold pulses in the DIII-D tokamak
journal, June 2019

  • Rodriguez-Fernandez, P.; White, A. E.; Howard, N. T.
  • Physics of Plasmas, Vol. 26, Issue 6
  • DOI: 10.1063/1.5096800

OMFIT Tokamak Profile Data Fitting and Physics Analysis
journal, January 2018


Main ion and impurity edge profile evolution across the L- to H-mode transition on DIII-D
journal, August 2018

  • Haskey, S. R.; Grierson, B. A.; Chrystal, C.
  • Plasma Physics and Controlled Fusion, Vol. 60, Issue 10
  • DOI: 10.1088/1361-6587/aad702

Perturbative transport modeling of cold-pulse dynamics in Alcator C-Mod Ohmic plasmas
journal, May 2019


Simulation of neutron emission in neutral beam injection heated plasmas with the real-time code RABBIT
journal, June 2019