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

Journal Article · · Fusion Science and Technology
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

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.

Research Organization:
General Atomics, San Diego, CA (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
Grant/Contract Number:
FC02-04ER54698; AC02-09CH11466
OSTI ID:
1424383
Journal Information:
Fusion Science and Technology, Vol. 73, Issue 2018; Related Information: Pages 1-15; ISSN 1536-1055
Publisher:
American Nuclear SocietyCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 34 works
Citation information provided by
Web of Science

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Cited By (12)

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
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
Propagation of input parameter uncertainties in transport models journal October 2018
Main-ion intrinsic toroidal rotation across the ITG/TEM boundary in DIII-D discharges during ohmic and electron cyclotron heating journal April 2019
Predict-first experiments and modeling of perturbative cold pulses in the DIII-D tokamak journal June 2019
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
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
Towards enhanced performance in fusion plasmas via turbulence suppression by MeV ions preprint January 2020

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