PTRANSP Predictive TRANSP Code Plans and Progress Presented by Glenn Bateman Lehigh University On behalf of the PTRANSP collaboration involving: General.

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PTRANSP Predictive TRANSP Code Plans and Progress Presented by Glenn Bateman Lehigh University On behalf of the PTRANSP collaboration involving: General Atomics Lawrence Livermore National Laboratory Lehigh University Princeton Plasma Physics Laboratory ITPA Meeting October 1-3, 2007

ITPA Naka, Japan October 2, 2007 Scientists Involved in Continuation of PTRANSP Project Doug McCune Steve Jardin Rob Andre K. Indireshkumar Don Pearlstein Lynda LoDestro Bill Meyer Tom Casper Lang Lao Holger St.John Phil Snyder Jon Kinsey Gary Staebler Arnold Kritz, PI Glenn Bateman Alexei Pankin Federico Halpern

ITPA Naka, Japan October 2, 2007 PTRANSP Code PTRANSP is the TRANSP analysis code used for predictive integrated modeling simulations –Code distribution used for TRANSP is also used for PTRANSP PTRANSP project has been funded at a level of $600K/year for two years –Funded as a continuation of NTCC project –Institutions involved GA, Lehigh Univ., LLNL (Tech-X), PPPL In May 2007, DOE renewed funding at the same level for an additional three year period –Goal: Increase level of predictive completeness and usefulness –Carry out tasks that support SciDAC FSP prototype projects PTRANSP builds on capabilities that exist in TRANSP code –TRANSP has a large user base and is well validated

ITPA Naka, Japan October 2, 2007 Need for the PTRANSP code PTRANSP will provide a full scale predictive integrated modeling capability during the next 5 to 10 years –TRANSP has a large world-wide user base 100 registered users of the PPPL Fusion Grid TRANSP service 4000 TRANSP simulations are carried out each year at PPPL and JET PTRANSP effort: Combining the models and capabilities that are scattered in other integrated modeling codes –Reduced models that are currently in ONETWO, CORSICA, TSC and BALDUR are being incorporated into PTRANSP –Verification and validation will provide a simulation code that is trusted by a large user base Advances in PTRANSP will contribute to SciDAC projects –Modules that are improved in PTRANSP are being used in SciDAC projects

ITPA Naka, Japan October 2, 2007 Vision for PTRANSP Fusion community continues to need a full-featured trusted integrated modeling code such as PTRANSP –For analysis of experimental data –For predictive simulations using theory-based and empirical models –For understanding the interactions among physical processes in tokamak plasmas PTRANSP will serve as a bridge to full fledged future Fusion Simulation Project capability by –Extending the existing software framework for predictive simulation –Providing a prototype for fusion simulations, and –Providing a rigorous method for verification of new modern, high performance, simulation frameworks as these become operational

ITPA Naka, Japan October 2, 2007 TRANSP and PTRANSP Funding Funding for TRANSP and PTRANSP from a variety of sources allows more complete development of PTRANSP Experimental projects –Need high fidelity source models for diagnostic simulation & analysis –Several thousand TRANSP runs per year Direct funding of the PTRANSP code Continued advances in NTCC modules are contributing to the development of PTRANSP –PTRANSP leverages module development in SciDAC projects For example, the Plasma State module and RF wave-plasma interaction modules

ITPA Naka, Japan October 2, 2007 Capabilities Recently Included in PTRANSP Newton’s method for numerically stable predictions using stiff transport models –Used with GLF23 and MMM95 anomalous transport models Choice of TEQ, ESC and other equilibrium solvers –Facilitates simulation of difficult equilibria Predictive pedestal model –Scalings for height and width of H-mode temperature pedestal Toroidal momentum transport –Momentum diffusivity from GLF23 or Weiland models Porcelli sawtooth model ELVis web-based graphical display –To view simulations in progress as well as archived simulations Object-oriented Plasma State data structure –Facilitates connection with other codes Upgraded NBI and RF heating and current drive sources Improved steering capability and robustness

ITPA Naka, Japan October 2, 2007 Newton’s Method Implemented in PTRANSP Formulation of Newton’s method developed by Steve Jardin –This formulation works together with the conventional tri-diagonal finite difference equations resulting from diffusion equations Currently implemented in PTRANSP and TSC  Tridiagonal finite difference eqns  = thermal diffusivity, which is a function of temperature gradients T’ = temperature gradient  = metric elements in transport eqns  = implicitness parameter ≥ ½ s =  t/(  x) 2

ITPA Naka, Japan October 2, 2007 Effect of Newton’s Method in PTRANSP Numerically induced oscillations in the GLF23 and MMM95 thermal diffusivity are eliminated by using Newton’s method –Example below uses 3 Newton iterations per time step with  = 1.0 In this example, thermal transport model is called 9 times per time step –Three times per Newton iteration to compute for T e and T i –Three Newton iterations per time step GLF23 After Using Newton’s Method GLF23 Before Using Time Smoothing

ITPA Naka, Japan October 2, 2007 When Implementing Modules the Devil is in the Details Implementing complicated models such as the GLF23 anomalous transport model is difficult –There are currently 67 input/output variables (scalars and arrays) in the routine that is used to call the GLF23 model It is easy to make a mistake that significantly affects the results –Correcting an error in defining radius in a previous implementation of GLF23 reduced predicted temperature profiles by more than 20% –Subtle choices, such as the inclusion of fast ion density or the use of alpha stabilization, have a noticeable effect on simulation results Sometimes a newly installed module yields unexpected and incorrect results –Defensive programming techniques are required It is important to review, verify and validate all features in the code that relate to the module being implemented

ITPA Naka, Japan October 2, 2007 PEDESTAL Module Implemented in PTRANSP The NTCC PEDESTAL module has been implemented in PTRANSP –Used to compute height and width of temperature pedestal at edge of H-mode discharges PEDESTAL module provides a predictive boundary condition for temperature profiles in PTRANSP –Static model for H-mode pedestal is being used at present It is important to have a predictive model for the pedestal –Since global confinement and core profiles depend on pedestal height Predictive pedestal density model will be implemented when density profiles are predicted in PTRANSP

ITPA Naka, Japan October 2, 2007 TEQ Module implemented in PTRANSP The NTCC TEQ equilibrium module has been implemented in PTRANSP for prescribed boundary equilibria –TEQ currently most reliable equilibrium solver in PTRANSP Equilibrium error contour plots shown for different solvers From Rob André, APS-DPP 2006 TEQ RZSOLVER VMEC ESC x10

ITPA Naka, Japan October 2, 2007 Examples of Source Modules Available in PTRANSP Neutral beam & fusion product deposition: –NUBEAM (Monte Carlo) RF sources: –TORIC, SPRUCE: Ion Cyclotron (low and high harmonic), Lower Hybrid: full wave solutions –GA-TORAY, LSC, GENRAY: Electron Cyclotron, Lower Hybrid: ray tracing solutions Fast ion accumulation; response to RF: –NUBEAM (Monte Carlo) –CQL3D (Fokker Planck; fast electrons also) Inputs to these modules include –Beam-line or RF antenna geometries, power, voltage, spectrum, plasma equilibrium magnetic fields, temperatures and densities Outputs include source densities of heat, momentum, particles and current drive

ITPA Naka, Japan October 2, 2007 Predictive Velocity Profile Evolution Momentum transport, as well as sources and sinks of momentum will be implemented to compute the plasma velocity profiles in the PTRANSP code –Anomalous momentum transport coefficients are computed using GLF23 or the new Weiland transport module –NBI momentum sources are computed using NUBEAM module The radial gradient of plasma velocity is a part of the ExB flow shear computation –The ExB flow shear rate is particularly important in the prediction of transport barriers, where flow shear stabilizes anomalous transport –Momentum, thermal and particle transport are needed for self-consistent computations of transport barriers

ITPA Naka, Japan October 2, 2007 Effect of Toroidal Rotation on Fusion Q Fusion performance found in ITER simulations with either ICRF or NBI heating is compared –P ICRF =P NBI =30MW Fusion power to electrons is shown as a function of time –Sudden periodic increases correspond to sawtooth oscillations –Increased ExB flow shear in NBI heated simulations results in higher fusion Q MMM95: 11.4 (ICRF) vs (NBI) GLF23: 7.9 (ICRF) vs. 8.7 (NBI) Central rotation frequency is shown as a function of time –Increases in   are due to P NBI increases –Mach number M=v  /C s ~0.05

ITPA Naka, Japan October 2, 2007 Porcelli Sawtooth Model in PTRANSP The Porcelli model is a widely used sawtooth model –Results using various implementations of Porcelli model have been compared with experimental data Observed effects of NBI and RF heating have been confirmed Porcelli trigger model has been implemented in PTRANSP –The Porcelli sawtooth trigger module has been installed in the NTCC Module Library after being tested in BALDUR code simulations Sawtooth periods computed in BALDUR simulations are compared with experimental data in Phys. Plasmas 13, (2006) –The trigger model calls the KDSAW module, already implemented in PTRANSP, contains Porcelli partial magnetic reconnection model It was found that the sawtooth period depends on the assumed fraction of magnetic reconnection, which alters the Kadomtsev reconnection model Implementation of Porcelli sawtooth trigger model is complicated by the different time step lengths in PTRANSP –Triggering has been implemented on the short transport time step

ITPA Naka, Japan October 2, 2007 Porcelli Sawtooth Trigger Criterion for JET Experimental data with vertical dotted lines marking sawtooth crash times - In this simulation, all the sawteeth are triggered as a result of criterion 3 (tearing modes) - Two parts of criterion 3 need to be satisfied for sawtooth crash to occur a) -c   < -  W < 0.5*  *i (red line between the blue and black) b)  *i < 3*   black red

ITPA Naka, Japan October 2, 2007 Plasma State Module The “Plasma State” –Is an emerging standard to share data time slices –Contains data for axisymmetric MHD equilibrium, plasma and source profiles (1-D and 2-D), as well as associated scalar data –Includes methods to read and write data Methods can involve interpolation from one grid to another –Can be stored in computer memory or as disk files –Provides a mechanism for communication between different codes Is not intended to be a restart file for PTRANSP simulations Will be possible to construct a time series of Plasma States –To provide data communication for comparison between time-dependent simulations as well as experimental results Plasma State to be used for communication between components in the SWIM SciDAC project –Loose coupling to distributed source model servers –File-based communication scheme will be utilized The Plasma State is being prepared as an NTCC Module with support from the PTRANSP project –Similar to XPLASMA but with a higher level interface –Will conform to NTCC Module standards, particularly documentation

D. McCune ELVis Web Visualization Client TRANSP - RPLOT

ITPA Naka, Japan October 2, 2007 PTRANSP Plans Predictive particle transport to evolve density profiles –Particle transport coefficients for hydrogenic and impurity ion species computed using MMM95, GLF23, and NCLASS modules Free-boundary TEQ equilibrium module with generalized Ohm’s law installed in PTRANSP –Database of input TEQ specifications for coils, external circuits and structural configurations will support most tokamaks Globally Convergent Newton Method Parallel (GCNMP) installed in the PTRANSP code –GCNMP will be refined for adaptive grids

ITPA Naka, Japan October 2, 2007 PTRANSP Plans TGLF will be installed as a successor to the GLF23 model –Since the TGLF model is computationally intensive, simulations will benefit from efficient parallel computing A new version of the Multi-Mode model is being developed and will be installed in PTRANSP –New Multi-Mode model includes momentum transport, multiple ion species, and improved finite beta effects A dynamic model for H-mode pedestal growth and ELM cycles will be implemented in PTRANSP –Dynamic ELM cycle model will be patterned after models currently used in ASTRA and JETTO

ITPA Naka, Japan October 2, 2007 PTRANSP Plans ELITE stability code to be installed in PTRANSP –ELITE is particularly well suited for computing the onset and width of the MHD instabilities that trigger ELM crashes Continuation of improvement in performance Improvements to simulation control –Options for automated feedback modification of source powers Standardized test problems will be developed to facilitate PTRANSP regression testing –Standardized time series may be developed for free-boundary equilibria, plasma profile data that is read in from datasets, heating power, current drive, initial & boundary conditions –Detailed validation studies will be carried out

ITPA Naka, Japan October 2, 2007 Predictive Density Profile Evolution Particle transport, sources, and sinks will be used to compute the evolution of density profiles in PTRANSP –MMM95, GLF23, and NCLASS modules are used to compute transport for hydrogenic and impurity ion species –Particle sources and sinks are already computed in PTRANSP –Particle transport equations will be patterned after those already used in BALDUR, JETTO and other transport codes Normally, particle transport equations are used to evolve multiple thermal ion profiles as well as fast ion profiles –Quasi-neutrality condition is then used to compute electron density Since all positive ion densities are added, the quasi-neutrality condition can never lead to a negative electron density Normalized density gradients, which are used in MMM95 and GLF23, also satisfy a quasi-neutrality condition Greater self-consistency results from predicting evolution of density profiles

ITPA Naka, Japan October 2, 2007 Free-Boundary TEQ Equilibrium Solver An enhanced free boundary TEQ equilibrium solver will be installed with tight coupling to magnetic diffusion solver –To be used for start-up and shut-down scenario studies, volt-second computations, simulation of ELM cycles, disruption studies, shape and vertical control system design, and coupling to edge/SOL models Ohm’s law will include hyper-resistive extensions –Fourth-order magnetic flux diffusion equation to model ELM crashes, neoclassical tearing modes, and sawtooth crashes –Recent simulations of hybrid DIII-D discharges simulate effects of tearing modes using hyper-resistivity (T. Casper, et al., IAEA 2006) Database of TEQ input specifications will be available for magnetic coils, external circuits, structural configurations –Database includes most tokamaks and will be added to as needed –Input database will facilitate simulations by allowing user simply to name the free boundary configuration to be used

ITPA Naka, Japan October 2, 2007 Globally Convergent Newton Method Parallel (GCNMP) GCNMP: Transport solver module developed by H. St.John –To be used in SWIM and NTCC/PTRANSP project Solves a generalized form of diffusive convective equations –For densities, temperatures, angular velocities and magnetic fields where vector u  [n 1 ….n n, T e, T i, FGH  Bp,  ] Number and subset of equations solved is user selectable –The remaining equations are run in “analysis mode” –Boundary conditions can be applied at different radial points GCNMP solver will use dynamic combination of steepest descent, line search and two trust region strategies –Switching from one method to next as needed for difficult problems

ITPA Naka, Japan October 2, 2007 New Transport Modules in PTRANSP New transport modules will be implemented in PTRANSP as they become available –PTRANSP will be used for a careful validation of transport models TGLF will be installed as a successor to the GLF23 model –TGLF transport is represented in terms of drift mode basis functions that have been calibrated using nonlinear GYRO simulations –The TGLF transport model is designed to be accurate from the plasma core to the base of the H-mode pedestal –TGLF model computes eigenvalues of 120x120 complex matrix for each toroidal mode number –Since the TGLF model is computationally intensive, simulations will probably require efficient parallel computing A new version of the Multi-Mode model is being developed –New Multi-Mode model includes momentum transport, multiple ion species, and improved finite beta effects

ITPA Naka, Japan October 2, 2007 PTRANSP Verification and Validation Standardized collection of plasma state datasets to be used for cross code verification and PTRANSP regression tests –Time dependent plasma state datasets will facilitate reproducible simulations by different integrated modeling codes –Standardized plasma state datasets will enable comparison between PTRANSP and first principles computations by SciDAC codes For more detailed studies of turbulence, RF heating and MHD instabilities Detailed comparisons will be made with wide range of scans of tokamak experimental data –For H-mode and dynamic advanced tokamak scenario discharges –To test TGLF, GLF23 and Multi-Mode anomalous transport models –To test other components as well as transport in the context of self-consistent predictive integrated simulations

ITPA Naka, Japan October 2, 2007 Planned Dynamic Edge Model in PTRANSP A dynamic model for H-mode pedestal growth and ELM cycles will be implemented in PTRANSP –Dynamic ELM cycle model will be patterned after models that are currently used in ASTRA and JETTO –ASTRA and JETTO simulation results have been compared with experimental data from JET and DIII-D Flow shear and magnetic shear stabilization of anomalous transport results in development of edge pedestal –Different modes of turbulence and different channels of ion and electron thermal transport are treated separately Each ELM crash is triggered by an MHD instability criterion –Initially, parameterizations of the peeling/ballooning MHD instability criterion will be used to trigger ELM crashes –Subsequently, ELITE code will be coupled to PTRANSP to compute ELM trigger and to estimate ELM width from eigenfunction structure

ITPA Naka, Japan October 2, 2007 Summary Predictive simulations are now being carried out with the PTRANSP code based on advances in the past 2-1/2 years Significant advances in the physics content will be added during the next 2-1/2 years –High-quality widely used modules for transport, equilibrium, sources, sinks and large scale instabilities all interacting together in one code –Comparison with experimental data facilitated by extensive data analysis infrastructure already built into TRANSP As a result of the effort planned for the next three years, PTRANSP will become significantly more comprehensive PTRANSP will serve as a bridge to high-performance SciDAC Fusion Simulation Projects

ITPA Naka, Japan October 2, 2007 Extra Slides

ITPA Naka, Japan October 2, 2007 ElVis Graphics Package ElVis is a Web/Java enabled graphics package for collaborative scientific work –See ElVis can be used for –Monitoring of running simulations while in progress –Examining output of completed simulations –Plotting experimental data Access using a web browser ElVis is used in CPES and SWIM SciDAC projects and in the TRANSP/PTRANSP project

D. McCune ElVis – Display Sequential Images Monitor Variables in netCDF Files CPES

ITPA Naka, Japan October 2, 2007 MPI Parallelization PTRANSP is a mix of widely different physics components –Some components can be parallelized more effectively than others –During each time step, physics components can involve an independent MPI computation mixed with sequential computations Must not endure PBS queue wait for every time step Loose coupling to distributed source model servers –Appropriate strategy for SWIM and PTRANSP projects –Sources characterized by long time scale: Collisional slowing down and pitch angle scattering times Current diffusion time Effects of sources need tome to accumulate –File-based communication schemes between components results in an overhead Tightly coupled framework –May be needed for FACETS project, but not necessarily from 1 st day

D. McCune MPI-Parallel Module Server Serial TRANSP Run (Client #1) Serial TRANSP Run (Client #2) Serial TRANSP Run (Client #N) Serial TRANSP Run (Client #3) … Input File* Package, e.g. XPLASMA** NetCDF state. Output File* Package, e.g. XPLASMA** NetCDF state. Server Queue MPI-Parallel TRANSP Module Server(s): NUBEAM monte carlo TORIC5 full wave GenRAY ray tracing CQL3D fokker planck GCNM transp. solver... … … **NTCC container module for equilibrium, profiles, distribution functions, etc. ( to be used for Fusion Simulation Project prototype and tested in TRANSP deployment. *viability of method depends on keeping files small. network 1 PBS wait per server File-based communications

ITPA Naka, Japan October 2, 2007 PTRANSP/SWIM Approach Long time scales reduce numerical challenge, but… –Collectively, source models still contain 100s of inputs and outputs NUBEAM, for example, has > 300 input and > 300 output variables –Each component has its own control mechanisms –Each component has its own grids TRANSP already presents unified interface to all sources –Sources are needed and funded by experimental projects –Stable source descriptions (as TRANSP namelist subsets) can be developed and named on a per-device basis We have developed a new software component, the plasma state, to communicate with a TRANSP server

D. McCune Communications Schema FACETS/SWIM (client): Free Boundary Transport Code with Coupled Edge Model Plasma State TRANSP (server): Source models; Transport Analysis. Experiment databases (MDS+) Device specific namelist template MPI-parallel source model servers TRANSP Output Database (MDS+) Time Slice Studies: GS2, GYRO, M3D, ORBIT… Tight coupling: core & edge transport solvers Loose coupling: core sources

ITPA Naka, Japan October 2, 2007 The Plasma State The Plasma State contains: –A plasma geometry and field configuration represented over “standard” coordinates –A collection of profiles (such as plasma temperatures and densities; sources and sinks) defined over coordinate grids. –Auxiliary information needed to fully identify profiles: Lists of plasma species Lists of neutral beams, RF antennas, etc. –Coordinates ( , ,  ) and (R,Z), v ll /v, energy –Grids: specific discretizations of coordinates –Profiles Each item has: –Unique name, units, label, owner and a unique integer ID R Z    [Rmin,Rmax] x [Zmin,Zmax] Rectangle encloses plasma.

ITPA Naka, Japan October 2, 2007 Object-Oriented Approach to Plasma State Each profile object consists of: –Reference to grid or grids covering a prescribed range and an interpolation method using NTCC PSPLINE module –Grids are ascending sequences that refer to coordinates Rho grids from 0 to 1; theta grids from 0 to 2  R grids from Rmin to Rmax; Z grids from Zmin to Zmax There can be multiple grids for each coordinate Axisymmetric MHD equilibria in “direct” (R,Z) representation and in “inverse” ( ,  ) representation List of plasma species –Temperatures, densities and velocities for each thermal species –Densities and kinetic information for each fast species List of neutral beams; beam heating and current drive profiles List of RF antennas; RF heating and current drive profiles

ITPA Naka, Japan October 2, 2007 Plasma State Fortran Module Public Module (built over NTCC software): –Access profiles on native grids directly: –ps%Ts(:, ) – Temperatures –ps%ns(:, ) – Densities –Subroutine calls for interpolation or particle and energy conserving “rezoning” I/O for Distributed Computing: –Save state to NetCDF file, Restore state from NetCDF file Fortran module and I/O methods are generated from a specification file using a Python script –Modification of the state definition is robust and convenient –Generator can be extended to add functionality For example, to capture the time evolution of a state

ITPA Naka, Japan October 2, 2007 Integrated SciDAC Projects and PTRANSP Three SciDAC projects (SWIM, CPES and FACETS) are developing new integrated modeling framework prototypes –These SciDAC projects emphasize integration of first-principles computations –SWIM (Simulation of RF Wave Interactions with MHD) will improve simulation of large scale instabilities, RF heating and current drive –CPES (Center for Plasma Edge Simulation) simulating pedestal formation and ELM cycles by coupling edge turbulence and MHD –FACETS (Framework Application for Core-Edge Transport Simulations) will couple edge and core plasma simulations Module development for PTRANSP will aid SciDAC projects –PTRANSP Plasma State module (data structure, interpolation, i/o) will be used directly in SciDAC projects

ITPA Naka, Japan October 2, 2007 PTRANSP Server Other codes can communicate with PTRANSP server –PTRANSP server provides unified way to compute sources –In server-client mode, each code has its own input and internal state –Because of large and complicated inputs/outputs, it is desirable to use components in their own code environment PTRANSP NUBEAM NBI module, for example, requires large amount of input data describing beam lines and large internal state –Requires more than 300 input and more than 300 output variables Collectively the source modules contain many 100s of inputs and outputs –Each component module has its own control mechanisms –Each component module has its own grid structure Plasma State developed as a software component to communicate with the PTRANSP server

ITPA Naka, Japan October 2, 2007 Model for Neoclassical Tearing Modes Planned for PTRANSP The ISLAND module to compute neoclassical tearing mode (NTM) magnetic island widths to be installed in PTRANSP –ISLAND module computes multiple island widths in tokamaks with arbitrary cross section and beta Transport is enhanced across each island for self-consistency –Tested in BALDUR implementation Electron Cyclotron Current Drive being implemented to model feedback stabilization of NTMs