Integrated Operation Scenarios ITPA NSTX-U Monday Physics Meeting, February 8, 2016 Yong-Su Na 1 Core Plasma Particle Transport Benchmark Activities in.

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Integrated Operation Scenarios ITPA NSTX-U Monday Physics Meeting, February 8, 2016 Yong-Su Na 1 Core Plasma Particle Transport Benchmark Activities in International Tokamak Physics Activity (ITPA) Integrated Operation Scenario (IOS) Group Yong-Su Na (Deputy Chair ) on behalf of ITPA IOS TG Department of Nuclear Engineering, Seoul National University Acknowledgement: C.E. Kessel, Dong-Hyun Na, A. Fukuyama, J. Garcia, N. Hayashi, F. Koechl, A. Polevoi, A. Wisitsorasak, X. Yuan

Integrated Operation Scenarios ITPA Yong-Su Na 2 NSTX-U Monday Physics Meeting, February 8, 2016 Goal of modelling activities in ITPA IOS TG Motivation of particle transport benchmarking Overview of particle transport benchmarking activity – Benchmarking guideline – Participating 1.5-D transport codes and modellers First results of particle transport benchmarking Discussion Next-step work Outline

Integrated Operation Scenarios ITPA Yong-Su Na 3 NSTX-U Monday Physics Meeting, February 8, 2016 Establish reliable integrated operation scenarios in ITER Address ITER urgent issues related with IOS Simulate and optimise ITER operation scenarios Model and simulate integrated control for ITER Improve predictive capability of integrated modelling Benchmark and verify existing models, modules, and codes Integrate models, modules, and codes for better prediction Goal of modelling activities in IOS

Integrated Operation Scenarios ITPA Yong-Su Na 4 NSTX-U Monday Physics Meeting, February 8, 2016 Short-term partially collaborative activities Establish reliable integrated operation scenarios in ITER Address ITER urgent issues related with IOS - Development of H, He scenarios - Ramp-down and plasma termination modelling - W transport modelling Simulate and optimise ITER operation scenarios Develop integrated control schemes for ITER - Burn control simulation - Integrated control simulation with actuator sharing Improve predictive capability of integrated modelling Benchmark and verify existing models, modules, and codes - Bootstrap current model benchmarking Integrate models, modules, and codes for better prediction - Pedestal modelling - Core-edge-SOL integrated modelling

Integrated Operation Scenarios ITPA Yong-Su Na 5 NSTX-U Monday Physics Meeting, February 8, 2016 Long-term fully collaborative activities sources (actuators) operation scenarios in ITER and beyond heat transport other ITPA TGs IMAS particle transport impurity & alpha transport momentum transport MHD (sawtooth, NTM, ELM, …)

Integrated Operation Scenarios ITPA Yong-Su Na 6 NSTX-U Monday Physics Meeting, February 8, 2016 Long-term fully collaborative activities sources (actuators) operation scenarios in ITER and beyond heat transport other ITPA TGs IMAS particle transport impurity & alpha transport momentum transport MHD (sawtooth, NTM, ELM, …) Benchmarking

Integrated Operation Scenarios ITPA Yong-Su Na 7 NSTX-U Monday Physics Meeting, February 8, 2016 Heat transport benchmarking C.E. Kessel et al, NF (2007)

Integrated Operation Scenarios ITPA Yong-Su Na 8 NSTX-U Monday Physics Meeting, February 8, 2016 Heat transport benchmarking M. Murakami et al, NF (2011)

Integrated Operation Scenarios ITPA Yong-Su Na 9 NSTX-U Monday Physics Meeting, February 8, 2016 Long-term fully collaborative activities sources (actuators) operation scenarios in ITER and beyond heat Transport other ITPA TGs IMAS particle transport impurity & alpha transport momentum transport MHD (sawtooth, NTM, ELM, …) Detailed validation of physics models, Development of theoretical models and codes are out of scope of these activities.

Integrated Operation Scenarios ITPA Yong-Su Na 10 NSTX-U Monday Physics Meeting, February 8, 2016 Plan for benchmarking activities Reassess performance of ITER operation scenarios heat transport particle transport impurity & alpha transport momentum transport MHD (sawtooth, NTM, ELM, …) control simulations (burn, profile, MHD, …) ITER Scenarios + Predictability sources (actuators)

Integrated Operation Scenarios ITPA Yong-Su Na 11 NSTX-U Monday Physics Meeting, February 8, 2016 Goal of modelling activities in ITPA IOS TG Motivation of particle transport benchmarking Overview of particle transport benchmarking activity – Benchmarking guideline – Participating 1.5-D transport codes and modellers First results of particle transport benchmarking Discussion Next-step work Outline

Integrated Operation Scenarios ITPA Yong-Su Na 12 NSTX-U Monday Physics Meeting, February 8, 2016 Importance of particle transport in ITER prediction How is the density established in L-mode and does affect the L-H transition, and ultimately controlled in flattop H-mode? What is the density and density profile evolution at the L-H transition which has significant implications for entering and staying in H-mode? How to set credible burn control strategies for the H-mode in the flattop phase which depends sensitively on the particle balance of the mixed D-T fuels, He and impurities? How is the density and density profile evolution during the I p ramp-down phase and the H-L transition phase? How much is the particle screening effect, charge exchange, recycling, and penetration of He and fuel into the core plasma which are central to understanding the dilution and tritium burnup? How much is the core fueling by pellet injection? How is the SOL/divertor plasma and its interactions with plasma facing components which sets the boundary conditions for the core transport? …

Integrated Operation Scenarios ITPA Yong-Su Na 13 NSTX-U Monday Physics Meeting, February 8, 2016 Particle transport modelling in ITER prediction Ultimate goal: modelling of integrated control of - Core density (burn control for DT) - Mode of operation (L, H) - ELM pacing - Divertor detachment - Impurity accumulation Responsibility of ITPA TGs: - Core transport models (T&C) - Pedestal models (PED) - Core boundary conditions (SOL/DIV) - Core transport solvers + integrated modelling (IOS) Core transport solvers: - Electron/ion transport simulation - Core fueling by pellets (permanent/instant models) - Sink with ELMs (permanent/instant models) - Core impurity transport (including control by ELM pacing) - Impact of boundary conditions (from SOL/DIV transport and control) - Efficiency of core fueling by gas puffing (penetration through the SOL)

Integrated Operation Scenarios ITPA Yong-Su Na 14 NSTX-U Monday Physics Meeting, February 8, 2016 Status of particle transport modelling Particle transport in the core plasma is often not treated regardless of its importance in integrated scenario simulations. – uncertainties of measurements to determine the separatrix density and the fuel sources (3-Dimentional) to validate transport models – complexity of multi-species impurity transport – complicated relationship with the SOL, divertor, and plasma facing materials

Integrated Operation Scenarios ITPA Yong-Su Na 15 NSTX-U Monday Physics Meeting, February 8, 2016 Particle transport benchmarking Goal – Verify agreement among various integrated modelling codes by approximating closely the expected scenario on ITER – Predict ITER plasmas more accurately based on knowledge accumulated from the benchmarking – Address the critical issues of ITER

Integrated Operation Scenarios ITPA Yong-Su Na 16 NSTX-U Monday Physics Meeting, February 8, 2016 Goal of modelling activities in ITPA IOS TG Motivation of particle transport benchmarking Overview of particle transport benchmarking activity – Benchmarking guideline – Participating 1.5-D transport codes and modellers First results of particle transport benchmarking Discussion Next-step work Outline

Integrated Operation Scenarios ITPA Yong-Su Na 17 NSTX-U Monday Physics Meeting, February 8, 2016 Steps in benchmarking STEP 1: Benchmarking of particle transport solvers with prescribed transport coefficients and sources at one time point in the current flattop Purpose: to ensure agreement and understand differences among particle transport solvers STEP 4: Benchmarking of time-evolution in whole discharge with prescribed transport coefficients and sources in time Purpose: to evaluate the impact of particle transport to scenario evolution STEP 2: Benchmarking of particle sources & sinks with prescribed transport coefficients at one time point in the current flattop Purpose: to compare source & sink models STEP 3: Sensitivity scans of transport coefficients at one time point in the current flattop Purpose: to evaluate the impact of particle transport to fusion performance STEP 5: Application of physics-based transport models Purpose: to predict particle transport in ITER

Integrated Operation Scenarios ITPA Yong-Su Na 18 NSTX-U Monday Physics Meeting, February 8, 2016 Steps in benchmarking STEP 1: Benchmarking of particle transport solvers with prescribed transport coefficients and sources at one time point in the current flattop Purpose: to ensure agreement and understand differences among particle transport solvers STEP 4: Benchmarking of time-evolution in whole discharge with prescribed transport coefficients and sources in time Purpose: to evaluate the impact of particle transport to scenario evolution STEP 2: Benchmarking of particle sources & sinks with prescribed transport coefficients at one time point in the current flattop Purpose: to compare source & sink models STEP 3: Sensitivity scans of transport coefficients at one time point in the current flattop Purpose: to evaluate the impact of particle transport to fusion performance STEP 5: Application of physics-based transport models Purpose: to predict particle transport in ITER Integrating with heat transport!

Integrated Operation Scenarios ITPA Yong-Su Na 19 NSTX-U Monday Physics Meeting, February 8, 2016 Guideline for Benchmarking Solving n e and T e, T i ITER baseline scenario at the plasma current flattop phase – I p = 15.0 MA, B T = 5.3 T at R = 6.2 m Basic assumptions – n Z = f z n e, quasi-neutrality – Set Helium density profile as n He (Φ) = n 0 [1 - (Φ/Φ edge ) 2 ] 2 Φ: toroidal magnetic flux n 0 = 0.95x10 19 /m 3 – Ignore NB fueling and current drive – Zero toroidal rotation – No sawtooth Plasma equilibrium: using a TSC result or approximate geometric values R 0 (m)a (m)κδZ mag (m)Volume (m 3 )

Integrated Operation Scenarios ITPA Yong-Su Na 20 NSTX-U Monday Physics Meeting, February 8, 2016 Guideline for Benchmarking Transport model setup – Edge particle source S(Φ) = S 0 exp{15 (Φ - Φ edge )/Φ edge } S 0 = 7.5x10 20 atom/m 3 – Core particle source by pellet fueling (continuous) S(Φ) = C*d 2 *(Φ/Φ edge ) 6.5 *[1-(Φ/Φ edge )] 8.5 /{d 2 +[(Φ/Φ edge )-0.5] 2 } C = 0.25x10 24, d = Pellets injected every 50 ms, so continuous source is ~ 50x smaller – Particle transport D(Φ) = D 0 + D 1 (Φ/Φ edge ) 2 for Φ < Φ ped D(Φ) = D 2 for Φ > Φ ped R 0 *v/D = V 0 *(Φ/Φ edge ) 1/2 D 0 = 0.5 m 2 /s, D 1 = 1.0 m 2 /s, D 2 = 0.11 m 2 /s V 0 = (positive is inward pinch)

Integrated Operation Scenarios ITPA Yong-Su Na 21 NSTX-U Monday Physics Meeting, February 8, 2016 Guideline for Benchmarking Transport model setup – Impurity specification Be: n Be /n e = 0.02, profile same as electrons Ar: n Ar /n e = , profile same as electrons W: n W /n e = 0.0 – Boundary condition n e (a) = 4.6x10 19 /m 3

Integrated Operation Scenarios ITPA Yong-Su Na 22 NSTX-U Monday Physics Meeting, February 8, 2016 Guideline for Benchmarking Transport model setup – Heat source P(Φ) = P 0 [1 - (Φ/Φ edge ) 1.5 ] 3.5 Normalise P 0 to match P total = 53.0 MW P elec /P total = 0.7, P ion /P total = 0.3 – Heat transport χ e,i (Φ) = χ 0 for Φ < Φ ped χ e,i (Φ) = χ ped exp{2.5 [(Φ - Φ ped ) / (Φ edge - Φ ped )] 2 } for Φ > Φ ped χ 0 = m 2 /s χ ped = 0.13 m 2 /s Φ ped /Φ edge = 0.88 – Boundary condition T e (a) = T i (a) = 150 eV

Integrated Operation Scenarios ITPA Yong-Su Na 23 NSTX-U Monday Physics Meeting, February 8, 2016 Main plasma parameters (reference) βNβN 2.0n e /n GW 0.74 τEτE 3.0 (including radiation)n e (0)1.0x10 20 /m 3 H (including radiation) 0.85x10 20 /m 3 W th 403 MJnene 0.9x10 20 /m 3 T i (0)24.6 keVn e (0)/ 1.18 T e (0)25.1 keV T i,ped 4.6 keV T e,ped 4.7 keV 1.51 PαPα 106 MW / P line 5.1 MW / P cycl 6.0 MW P brem 17.1 MW P net 135 MW ASTRA v.6

Integrated Operation Scenarios ITPA Yong-Su Na 24 NSTX-U Monday Physics Meeting, February 8, 2016 Participants of the activity 1.5-D transport CodeModeller ASTRA (v.6 + α)Dong-Hyun Na (Seoul National University) Yong-Su Na (Seoul National University) ASTRA (v.6x + v.7) A. Polevoi (ITER IO) CRONOSJ. Garcia (CEA) FASTRANJ.M. Park (ORNL) Kyungjin Kim (Seoul National University) JINTRAC (JETTO)F. Koechl (CCFE) TASK/TRA. Wisitsorasak (King Mongkut's University of Technology Thonburi, Thailand) A. Fukuyama (Kyoto University) TOPICSN. Hayashi (JAEA) TRANSPX. Yuan (PPPL) Yong-Su Na (Seoul National University)

Integrated Operation Scenarios ITPA Yong-Su Na 25 NSTX-U Monday Physics Meeting, February 8, 2016 Goal of modelling activities in ITPA IOS TG Motivation of particle transport benchmarking Overview of particle transport benchmarking activity –Benchmarking guideline – Participating 1.5-D transport codes and modellers First results of particle transport benchmarking Discussion Next-step work Outline

Integrated Operation Scenarios ITPA Yong-Su Na 26 NSTX-U Monday Physics Meeting, February 8, 2016 Particle transport

Integrated Operation Scenarios ITPA Yong-Su Na 27 NSTX-U Monday Physics Meeting, February 8, 2016 Particle transport

Integrated Operation Scenarios ITPA Yong-Su Na 28 NSTX-U Monday Physics Meeting, February 8, 2016 Particle transport

Integrated Operation Scenarios ITPA Yong-Su Na 29 NSTX-U Monday Physics Meeting, February 8, 2016 Z eff Particle transport

Integrated Operation Scenarios ITPA Yong-Su Na 30 NSTX-U Monday Physics Meeting, February 8, 2016 Goal of modelling activities in ITPA IOS TG Motivation of particle transport benchmarking Overview of particle transport benchmarking activity – Benchmarking guideline – Participating 1.5-D transport codes and modellers First results of particle transport benchmarking Discussion Next-step work Outline

Integrated Operation Scenarios ITPA Yong-Su Na 31 NSTX-U Monday Physics Meeting, February 8, 2016 Errors in the transport solver? Different equilibrium? – some using the prescribed one but the others solving the current diffusion equation Possible reasons for disagreement Radial grid? Solving ion transport? Different definition of transport coefficients? Different treatment of impurities? …

Integrated Operation Scenarios ITPA NSTX-U Monday Physics Meeting, February 8, 2016 Yong-Su Na 32 Check particle flow balance ASTRA v.6TOPICS

Integrated Operation Scenarios ITPA NSTX-U Monday Physics Meeting, February 8, 2016 Yong-Su Na 33 Transport equations being solved ASTRA CRONOS TRANSP (PTSOLVER)

Integrated Operation Scenarios ITPA NSTX-U Monday Physics Meeting, February 8, 2016 Yong-Su Na 34 Some codes solve ion transport JINTRAC TOPICS

Integrated Operation Scenarios ITPA NSTX-U Monday Physics Meeting, February 8, 2016 Yong-Su Na 35 Some codes solve ion transport JINTRAC - Simulation rerun with the following modified settings: Additional pinch terms to accommodate for differences between solutions obtained with electron vs. ion particle transport equations in case of different impurity density profile shape: That way, the electron flux that would be obtained with an electron transport equation with fixed impurities can be calculated with the ion particle transport equations. - The boundary condition of main ion densities at the separatrix has been adjusted in order to match n e (a) = 4.6x10 19 /m 3. TOPICS

Integrated Operation Scenarios ITPA Yong-Su Na 36 NSTX-U Monday Physics Meeting, February 8, 2016 JINTRAC without correction Some codes solve ion transport JINTRAC with correction

Integrated Operation Scenarios ITPA Yong-Su Na 37 NSTX-U Monday Physics Meeting, February 8, 2016 Effect of.vs. in pinch term Blue: Red: TOPICSJINTRAC

Integrated Operation Scenarios ITPA Yong-Su Na 38 NSTX-U Monday Physics Meeting, February 8, 2016 Treatment of impurities TRANSP solved impurity ionisation so that non-full striped impuritis (Be, Ar) are used. Z eff

Integrated Operation Scenarios ITPA Yong-Su Na 39 NSTX-U Monday Physics Meeting, February 8, 2016 Resulting heat transport (example)

Integrated Operation Scenarios ITPA Yong-Su Na 40 NSTX-U Monday Physics Meeting, February 8, 2016 Goal of modelling activities in ITPA IOS TG Motivation of particle transport benchmarking Overview of particle transport benchmarking activity – Benchmarking guideline – Participating 1.5-D transport codes and modellers First results of particle transport benchmarking Discussion Next-step work Outline

Integrated Operation Scenarios ITPA Yong-Su Na 41 NSTX-U Monday Physics Meeting, February 8, 2016 Steps in benchmarking STEP 1: Benchmarking of particle transport solvers with prescribed transport coefficients and sources at one time point in the current flattop Purpose: to ensure agreement among particle transport solvers STEP 4: Benchmarking of time-evolution in whole discharge with prescribed transport coefficients and sources in time Purpose: to evaluate the impact of particle transport to scenario evolution STEP 2: Benchmarking of particle sources & sinks with prescribed transport coefficients at one time point in the current flattop Purpose: to compare source & sink models STEP 3: Sensitivity scans of transport coefficients at one time point in the current flattop Purpose: to evaluate the impact of particle transport to fusion performance STEP 5: Application of physics-based transport models Purpose: to predict particle transport in ITER

Integrated Operation Scenarios ITPA Yong-Su Na 42 NSTX-U Monday Physics Meeting, February 8, 2016 STEP 2 STEP 2: Benchmarking of particle sources & sinks with prescribed transport coefficients at one time point in the current flattop Purpose: to compare source & sink models Particle pinch verification Particle source verification – Core source Pellet source: size, frequency, velocity (limits from hardware…).vs Continuous core source: atoms/m 3 /s and profile shape – Edge source How large and how deep should edge source be in H-mode Edge density specification, what do we base this on? D and v magnitudes, target τ p and τ P *, relate to τ E n e (a), S edge, S core, D, v  solutions (uniqueness) n e (Φ), ….. – Examine range from flat n e to n e0 /n e < Probable usage of ITER Baseline discharges from various devices to identify particle transport terms and behaviors.

Integrated Operation Scenarios ITPA Yong-Su Na 43 NSTX-U Monday Physics Meeting, February 8, 2016 Goal of modelling activities in ITPA IOS TG Motivation of particle transport benchmarking Overview of particle transport benchmarking activity – Benchmarking guideline – Participating 1.5-D transport codes and modellers First results of particle transport benchmarking Discussion Next-step work Summary

The particle source term results from the following contributions: respectively, ionization source from neutrals (wall recycling, gas puffing, etc), NBI, optional additional source ‘EXT’, particle losses induced by toroidal magnetic field ripple. The electron flux can be calculated either as the sum of a diffusive and a convective terms: or as a full transport matrix formulation: CRONOS

TASK/TR

Simulation conditions in TOPICS - Solve density (n DT =2n D =2n T ) and Obtain stationary-state profile at flattop phase, as a first step ρ : normalized minor radius defined by square root of toroidal flux - V pinch = 0.3 D / r ( r : volume-averaged minor radius ) - Pellet source : Gaussian at ρ=0.675, FWHM Δρ=0.225, 3.75e20 /s - MHD equilibrium : read G-EQDSK file - Other conditions are same as given ones. - Fusion cross section : Bosh-Hale (used in previous ITPA benchmark)

Settings in TOPICS Normalized radius defined by square root of toroidal flux cut diverging pinch in ρ<0.1 small difference due to "r" definition difference

Results in TOPICS given More peaked density profile than Kessel data ?? It is confirmed that Bosh-Hale reaction model can produce almost the same α-heating power as Kessel data.

Other questions on the Kessel data Difference of Z eff value between one in the data and re-evaluated value from n e, n He, n Be, n Ar (δZ eff ~ 0.02 (core) (edge)) Non full striped impuritis (Be, Ar) assumed ?

JINTRAC Simulation rerun with the following modified settings: -Additional pinch terms to accommodate for differences between solutions obtained with electron vs. ion particle transport equations in case of different impurity density profile shape: That way, the electron flux that would be obtained with an electron transport equation with fixed impurities can be calculated with the JETTO ion particle transport equations:

JINTRAC core particle transport equations Main ion transport equations (JETTO): Impurity transport equations (SANCO): where are ionisation and recombination sources and sinks for impurity species with indices i and the charge z where n i is the density of the i-th hydrogenic species, V’ = dV/d , S i includes sources and sinks (neutrals, pellets, fusion losses etc.).

Pinch velocity has appeared as a definition issue among codes (maybe just TSC) Particle transport eqn in TSC: dN/dt = d/d  [ D V’ |grad(  )| 2 ( dn/d  + V o n/  ) ] + S(  ) V o = dimensionless = v*r/D N = V’n d’s are actually partials From Irina V. for ASTRA: d/dt(V’f) = d/d  [ V’ ( D df/d  – v f ) ] + V’S  d’s are actually partials reference