Last Modified:Wednesday, 27-Oct-2021 09:26:01 BST

Manual for the PR08 Release of the ITPA International

Multi-Tokamak Profile Database

Standard list of variables and file formats

ITPA Confinement Modelling and Database Group

This is the definitive source of information on data formats and access to the 2008 Public Release (PR08) of the ITPA Multi-tokamak Confinement Profile Database.

Introduction

Definition of local transport quantities

Comments Data

OD Data: global parameters

OD file format and example

1D description file: time traces

2D description file: Evolving radial profiles

Index Format for time evolving radial grids

Format of 1D and 2D files

File naming convention

Accessing the Profile Database via MDSplus

Software

Introduction

The International Multi-tokamak Profile Database is served from a computer at UKAEA Culham:

http://tokamak-profiledb.ccfe.ac.uk

The profile database stores well documented discharges that are accessible to the fusion community through ftp, http, and MDSplus.
A PR08 discharge is composed of:

A Comments file which is a text file containing general information about the responsible scientist who produced the data, the analysis code and miscellaneous other information.
a 0D description file containing the global parameters of the discharge selected at some relevant time slices corresponding to the various phases of the discharge.
a 1D description file containing the time evolution of scalar quantities as a function of time.
a 2D description file containing the radial profiles of quantities as a function of time and additional information about the plasma geometry.

This document establishes what set of variables are provided for each description file together with the definition of these variables and the standard format in which they are provided. The data are stored as follows:

via anonymous ftp (also browsable via http) the directory itpa_pr08 contains a list of directories corresponding to tokamaks from which discharges are available.
inside each tokamak directory is a list of directories corresponding to a particular discharge themselves containing the comments file, 0D, 1D and 2D description file for that discharge.

This document describes, for each of the description files, the list of relevant plasma paramaters they contain together with the file format in which they are provided.

Definition of local transport quantities:

The primary role of the profile database is to supply profile data allowing the derivation of local transport coefficients and their comparison with predictions from transport models. It is assumed that the transport models will focus on thermal electron and main thermal ion transport. Therefore, the database seeks to provide the radial profiles as a function of time of all the relevant terms needed in the conservation equations for these two species.
Throughout this document the following definition are adopted:
The radial coordinate is the normalized toroidal flux defined as follow:
ρ=(φ/φ_a)^0.5, where φ is the total toroidal flux enclosed by the given magnetic surface and φ_a is the total toroidal flux enclosed by the plasma separatrix (see 1D signal # 29: PHIA). ρ goes from 0 in the center to 1 at the separatrix.

We note <.> the surface average operator defined by < B.∇ A > = 0 whatever A(R,Z), V(ρ) the volume enclosed by the surface of label ρ, and S(ρ) is the corresponding surface area.

The particle and energy conservation equations can be written:

The compressional term CMP is theory dependent and needs to be specified for each model. For instance in the Braginskii model: CMP=-n_α k T_α < ∇ v_α > with Γ_α = n_α v_α and where α stands either for thermal electrons or for main thermal ions.
The plasma surface area is given by: S(ρ)=V'(ρ) < | ∇ ρ | >

Quantity:	Corresponding signal number and name in this manual:
ϕ_α	29.PHIA
n_α	9. NE, 38. NM1, 42. NM2, 42b. NM3, 46. NIMP
T_α	1. TE, 5. TI
dn_α/dt	60.DNER
dW_α/dt	58. DWER, 59. DWIR
S(ρ)	72. SURF
<\|∇ρ\|>^(*)	73. GRHO1
< \|∇ρ\|² >^(*)	74.GRHO2
χ_α	36. CHIE, 37. CHII (Note that the definition of χ_α does not include the <\|∇ρ\|²>

(*) ρ is demensionless and the gradient is with respect to the (R,Z) coordinates, so these quantities are in m^-1 and m^-2 respectively.

Comments Data

The comments file contains all the information users need to known about the discharge or the way the data has been obtained but that doesn't appear either in this manual or in the 0D, 1D or 2D files detailed in the next chapters. This text file should contain the following fields:

**PR08 COMMENTS Variables**
0D Variable	Units	Data Type	Brief Description	Full Description
Additional:	ADDITIONAL	String	any additional information	any additional information
Analysis code(s):	ANAL_CODES	String	codes used for data analysis	codes used for data analysis
Assumptions:	ASSUMPTION	String	main assumptions made in the analysis	main assumptions made in the analysis
Contact person:	CONTACT	String	contact person at the experiment	contact person at the experiment
Date of analysis:	ANAL_DATES	String	date of analysis	date of analysis
Date of shot:	SHOT_DATE	String	date of shot	date of shot
Institution:	INSTITUTION	String	institution	institution
Publication:	PUBLICATION	String	publication	publication
Pulse number:	SHOT	String	shot number	shot number
Run number:	RUN_NUMBER	String	run number	run number
Shot description:	DESCRIPTION	String	summary of useful information describing the shot and giving the purpose of the experiment	summary of useful information describing the shot and giving the purpose of the experiment
Tokamak:	TOKAMAK	String	tokamak name	tokamak name

This information is crucial to provide users/modellers with a compact overview of the discharges. Data providers should feel free to add in this file any information they think might be relevant to the use of this data. Comments data should list codes and assumptions used in the data analysis. For instance EFIT for equilibrium, PENCIL for NBI deposition profile, ONETWO for transport, "flat Zeff was assumed" or "It was asumed that Te = Ti" etc

See this example comments file

OD Data: global parameters

It is expected that for each discharge sent to the database one or several relevant time slices will be selected at which time the following global data - were relevant - will be provided.

These time slices are used to summarize the discharge and help users locate specific regimes in the database. However, they are not necessarilly the same time slices as used in the 2D files described below (indeed 2D Ufiles may contains hundreds of time slices whereas for the 0D file only a few time slices will in general be sufficient).

Additional definitions are given at the end of this chapter for quantities used to define parameters figuring in this standard list.

PR08 0D Variables

0D Variable

Units

Data Type

Brief Description

Full Description

AMIN

Real

minor radius

The horizontal plasma minor radius in meters from an MHD equilibrium fit or a formula based on a number of equilibria (ASDEX).
Normal level of accuracy is ASDEX (± 1%), D3D (± 0.5%), JET (± 3%), JFT2M (± 3%), PBXM (± 3%), PDX (± 3%).

AREA

m^2

Real

poloidal cross sectional area

Area of poloidal plasma cross section in m², ideally determined from an MHD equilibrium fit, or alternatively from the formula:
AREA = &pi &kappa AMIN².

AUXHEAT

String

auxiliary heating

Type of auxiliary heating. Each scheme is labelled by:

NONE:	No Auxiliary heating
NB:	Neutral Beam Injection
IC:	Ion Cyclotron Resonance Heating
EC:	Electron Cyclotron Resonance Heating
LH:	Lower hybrid
IBW:	Ion Bernstein Waves.

This variable is set by concatenating the strings for each heating scheme which is operating: eg "NBIC" for combined NBI + ICRH. It is recommended that the concatenation order should follow the order of appearance of strings in the above table.

BEPDIA

Real

absolute poloidal beta from diamagnetic loop

Absolute corrected poloidal beta from diamagnetic loop

BEPMHD

Real

absolute poloidal beta

Absolute poloidal beta computed from the MHD equilibrium fit.

BETMHD

Real

absolute toroidal beta

Absolute toroidal beta computed from the MHD equilibrium fit.

BETNMHD

Real

normalised toroidal beta

Normalised toroidal beta computed from the MHD equilibrium fit. BETNMHD=100*BETMHD*AMIN(m)*BT(T)/IP(MA) = 10⁸*BETMHD*AMIN*BT/IP

BGASA

amu

Integer

mass number of beam gas

Mass number of the neutral beam gas. Possible values are: 1 (Hydrogen), 2 (Deuterium), 3 (³H_e) or 4 (⁴H_e). & C

BGASA2

amu

Integer

mass number of 2nd beam gas (JET)

Mass number of the second neutral beam gas (JET only). Possible values are: 1 (Hydrogen), 2 (Deuterium), 3(³H_e) or 4 (⁴H_e). & C

BGASZ

Integer

charge number of beam gas

Charge number of the neutral beam gas. Possible values are: 1 (Hydrogen or Deuterium) or 2 (Helium). & C

BGASZ2

Integer

charge number of 2nd beam gas (JET)

Charge number of the second neutral beam gas (JET only). Possible values are: 1 (Hydrogen or Deuterium) or 2 (Helium). & C

BPFOOT

Real

Flux surface averaged poloidal magnetic field at RFOOT

BSOURCE

Integer

main beam power fractions F1*10000+F2*100+F3 (F1 F2 F3 all to nearest %)

The power fractions injected by neutral beam eg P₁ = 80%, P₂= 10% and P₃= 10% then BSOURCE = 801010.

BSOURCE2

Integer

auxiliary beam power fractions F1*10000+F2*100+F3 (F1 F2 F3 all to nearest %)

The power fractions injected by neutral beam with the second source (JET only). For 89-90 data the possibilities for BSOURCE and BSOURCE2 are 781606 for 80kV D, 652114 for 140kV D, 990000 for ³H_e or ⁴H_e beams.

Real

vacuum toroidal magnetic field at geometric axis

vacuum toroidal magnetic field at geometric axis: +ve BT is anti-clockwise when viewed from above

COCTR

Real

fraction of beam power co-injected (ie parallel to plasma current)

Fraction of beam power co-injected (ie parallel to plasma current), as compared to the total beam power injected. COCTR = P_co / (P_co + P_ctr) and lies between 0 and 1.

CONFIG

String

Plasma configuration

Plasma configuration. Possible values are:

SN:	Single null (generic)
LSN:	Lower single null
USN:	Upper single null
DN:	Double null
LIM:	Limiter (generic)
TOP, BOT, OUT, IN:	description of limiter position
IW:	Inner wall

DATE

Integer

shot date YYYYMMDD

The date the shot was taken. The format is YYYYMMDD.

DELTA

Real

mean triangularity

The mean triangularity of the plasma boundary from an MHD equilibrium fit.
Normal level of accuracy is ASDEX (Na), D3D (± 10%), JET (±10%), JFT2M (± 10%), PBXM (± 25%), PDX (Na).

DELTA95

Real

mean triangularity at 95 % poloidal flux

The mean triangularity of the surface which encloses 95 % of the poloidal flux from an MHD equilibrium fit.

DELTAL

Real

lower triangularity

The lower triangularity of the plasma boundary from an MHD equilibrium fit.

DELTAL95

Real

lower triangularity at 95 % poloidal flux

The lower triangularity of the surface which encloses 95 % of the poloidal flux from an MHD equilibrium fit.

DELTAU

Real

upper triangularity

The upper triangularity of the plasma boundary from an MHD equilibrium fit.

DELTAU95

Real

upper triangularity at 95 % poloidal flux

The upper triangularity of the surface which encloses 95 % of the poloidal flux from an MHD equilibrium fit.

DIPDT

A/s

Real

Time derivative of plasma current in A/s

DIVMAT

String

divertor material

The material of the divertor tiles. Possible values are: SS for stainless steel, C or CC for carbon, TI1 or TI2 for titanium, BE for beryllium or C/BE for carbon at the top and beryllium at the bottom.

DNELDT

m^-3/s

Real

time derivative of central line averaged electron density

The time rate of change of NEL in m^-3/s.
Normal level of accuracy is similar to NEL.

DNEVDT

m^-3/s

Real

time derivative of volume averaged electron density

The time rate of change of NEV in m^-3/s.

DWDIA

J/s

Real

Time derivative of WDIA.

DWMHD

J/s

Real

Time derivative of WMHD.

DWTOT

Js^-1

Real

time derivative of total plasma energy content

Time rate of change of WTOT in Joules / s .

ECHFREQ

Real

ECH frequency

ECH frequency in Hz

ECHLOC

String

ECH launch location

Location of ECH launch, IN identifies waves launched from the high field side or inside of the vessel and OUT is from the low field side.

ECHMODE

String

mode of ECH waves

Mode of ECH waves, O is ordinary and X is extraordinary.

ECHRLOC

Real

ECH resonance layer radius (&rho_n)

ECH resonance layer radius (&rho_n).

ENBI

Real

neutral beam energy

Neutral beam energy weighted by power in volts. This quantity is calculated from &sum E_iP_i/&sum P_i where E_i is the main beam energy for source i and P_i is the beam power for source i.

ENBI1

Real

Primary beam acceleration voltage in V.

ENBI2

Real

Secondary beam acceleration voltage in V.

EVAP

String

evaporated wall conditioning material

The evaporated material used to cover the inside of the vessel. Possible values are:

BORO generic for boron

BOROA (B₂H₆ + CH₄ + H₂)

BOROB (B₂H₆ + H₂)

BOROC (B₂D₆ + He)

CARB generic for carbon

CARBH (CH₄ + D₂)

TI for titanium

BE for beryllium

NONE for no evaporation.

FPERP

Real

Fraction of beam power injected perpendicular as compared to the total beam power injected

GRADTE

eV/m

Real

Electron temperature gradient on outboard mid-plane immediately inside RFOOT

GRADTI

eV/m

Real

Ion temperature gradient on outboard mid-plane immediately inside RFOOT

H89P

Real

Ratio of confinement time to ITER89P L-mode scaling law

IBOOT

Real

Total bootstrap current.

Total bootstrap current, calculated by a neoclassical code.

IBWFREQ

Real

IBW frequency

Frequency of IBW in Hz.

ICANTEN

String

ICRH antenna phasing

Antenna phasing. Possible Values are DIPOLE or MONOPOLE.

ICFREQ

Real

ICRH frequency

Frequency of ICRH waves in Hz.

ICSCHEME

String

ICRH heating scheme

ICRH heating scheme. Possible Values: HMIN for H minority, HE3MIN for ³He minority or H2NDHARM for 2nd harmonic H heating respectively.

IGRADB

Integer

ion gradB drift towards/away (1/-1) from Xpoint

Indicates when CONFIG = SN whether the ion gradB-drift is towards (1) or pointing away from (-1) the X-point.

INDENT

Real

indentation

Indentation of the plasma determined from an MHD equilibrium fit.
Normal level of accuracy is ASDEX (Na), D3D (Na), JET (Na), JFT2M (Na), PBXM (± 15%), PDX (Na).

Real

plasma current

plasma current: +ve IP is anti-clockwise when viewed from above

ISEQ

String

parameter scan identifier

Parameter scan identifier
Possible options for ASDEX are:

ISEQ	Explanation
NONE	No particular scan
G1	Comparison shots for Helium program
NE1	Density variation
HT1	Search for high confinement times
EF11	Search for long ELM-free periods
SP11	Spectroscopic investigations
HBE1	High beta investigations, T_i profile measurements
HBE2	High beta investigations, T_i profile measurements
HBE3	High beta investigations, T_i profile measurements
P1	PNBI scan
P2	PNBI scan
QC1P3	QCYL and PNBI scan
BT1	BT scan
BT2 P4	BT and PNBI scan
BT3	BT scan
BT4	BT scan
BT5	BT scan
BT6	BT scan
BT7	BT scan

Possible options for JFT2M are:

ISEQ	Explanation
NONE	No particular scan
AM1	AMIN scan with Ip = 0.22MA (same Q95)
IP1	1st Ip scan with Bt = 1.25T
IP2	2nd Ip scan (Hydrogen)
IP3	3rd Ip scan (Deuterium)
BS1	Scan of 801010 (CO or CTR) and 603010 (CO or CTR)
BT1	Bt scan with Ip = 0.16MA
BT2	Bt scan with Ip = 0.21MA
EB1	ENBI scan with BSOURCE = 603010
EB2	ENBI scan with BSOURCE = 801010
G1	Intense gas puff for comparison with H pellet H mode
G2	Intense gas puff for comparison with D pellet H mode
G3IP2	2nd Ip scan (Hydrogen) with intense gas puffing
G4IP3	3rd Ip scan (Deuterium) with intense gas puffing
IE1	IEML and PNBI scan looking for steady state H mode region
P1	PNBI scan by CO or CTR with Ip = 0.25MA
P2	PNBI scan by CO + CTR with Ip = 0.24MA
P3IP4NE1	PNBI , IP and NEL scan in Hydrogen plasma
P4IP5NE2	PNBI , IP and NEL scan in Deuterium plasma
PE1	Hydrogen pellet into Hydrogen plasma
PE2	Deuterium pellet into Deuterium plasma
XP1	XPLIM scan with Ip = 0.24MA

No options available for D3D, JET, PBXM and PDX.

ITB

String

ITB flag

Flag for ITB conditions with possible values: "ITB" if an ITB is present, "PREITB" immediately before the ITB onset, and "NOITB" if no ITB is present

ITBTIME

Real

Time of ITB triggering.

ITBTYPE

String

Type of ITB.

Type of ITB with possible values: "NONE", "TI", "TE", "NE", and concatenations of these (eg "TITENE")

KAPPA

Real

plasma elongation

The plasma elongation determined from an MHD equilibrium fit or a formula based on a number of equilibria (ASDEX). Normal level of accuracy is ASDEX (± 1%), D3D (± 1%), JET (± 5%), JFT2M (± 10%), PBXM (± 10%), PDX (k = 1 for all records, ± 10%).

KAPPA95

Real

elongation at 95 % poloidal flux

Elongation of the surface which encloses 95 % of the poloidal flux from an MHD equilibrium fit.

LHFREQ

Real

LH frequency

Frequency of LH waves in Hz.

LHNPAR

Real

LH parallel mode number

LH parallel mode number.

Real

internal inductance

Internal plasma inductance (ideally from MHD equilibrium):
l_i=2 &int B_p²dV / ( &mu₀² I_p² R_geo )

LIMMAT

String

limiter material

The material of the limiters. Possible valuesare: BE for beryllium or C for carbon.

NE0

m^-3

Real

central electron density

Central electron density in m^-3.

NE95

m^-3

Real

electron density at 95% poloidal flux surface

NEFOOT

m^-3

Real

electron density at an ITB foot

NEL

m^-3

Real

central line averaged electron density

Central line average electron density in m^-3 from interferometer.
For JET NEL has been approximated by:
ohmic: NEL ~ exp {2.931 +0.873 log (NEV) + 0.064 log (NEØ)}
H-mode: NEL ~ exp {3.745 +0.825 log (NEV) + 0.092 log (NEØ)} If no measurement is available, the variable NELFORM indicates if NEL is measured or approximated.
Normal level of accuracy is ASDEX (± 2%), D3D (± 2 x 10¹⁸ m^-3), JET (± 8%), JFT2M (± 2%), PBXM (± 5%), PDX (± 5%).

NESHOULD

m^-3

Real

electron density at an ITB shoulder

NEV

m^-3

Real

volume averaged electron density

Volume average electron density in m^-3.

NFASTnA

amu

Real

mass number of nth fast ion species <=> 2D variable NFASTn

mass number of nth fast ion species corresponding to 2D variable NFASTn with 1 &le n &le 9

NFASTnZ

Real

atomic number of nth fast ion species <=> 2D variable NFASTn

atomic number of nth fast ion species corresponding to 2D variable NFASTn with 1 &le n &le 9

NMnA

amu

Real

mass number of nth thermal ion species <=> 2D variable NMn

mass number of thermal ion species corresponding to 2D variable NMn with 1 &le n &le 9

NMnZ

Real

atomic number of nth thermal ion species <=> 2D variable NMn

atomic number of thermal ion species corresponding to 2D variable NMn with 1 &le n &le 9

PECH

Real

ECH power coupling to plasma

ECH power in watts coupled to the plasma. Zero if no ECH is applied.
Normal level of accuracy is D3D (± 10%). ASDEX, JET, JFT2M,PBXM, PDX: Na.

PELLET

String

Pellet material information and side of launch

NONE if no pellets
H/D/LI for the pellet material
concatenated with injection field side (HFS, LFS)

PERFDUR

Real

duration of the high performance phase

duration of the high performance phase, defined as the time (in s) during which the discharge has >85% of its maximum stored energy. This indicates how stationary the discharge is.

PGASA

amu

Real

mean mass number of main plasma ions

Mean mass number of the plasma ions. Values typically ranging from 1.0 to 3.0 in hydrogenic plasmas, and up to 4.0 in He plasmas

PGASZ

Real

mean charge number of main plasma ions

Mean charge number of the main plasma ions. Values typically ranging from 1.0 in hydrogenic plasmas to 2.0 in Helium.

PHASE

String

plasma phase

The phase of the discharge at TIME. Possible values are:

OHM :	Ohmic
L :	L-mode
LHLHL :	H-mode with frequent L H transitions
H :	ELM-free H-mode
HSELM :	H-mode with small ELMs
HGELM :	H-mode with large ELMs
HELM :	H-mode with ELMs (generic)
HGELMH :	H-mode with high frequency large ELMs
HYB :	Hybrid regime
VH :	VH-mode
PEP :	PEP mode

PIBW

Real

IBW power coupling to plasma

IBW power in watts coupled to the plasma. Zero if no IBW is applied.

PICRH

Real

ICRH power coupling to plasma

ICRH power in watts coupled to the plasma. Zero if no ICRH is applied.
Normal level of accuracy is JET (± 10%). ASDEX, D3D, JFT2M, PBXM, PDX: Na.

PIMPA

amu

Real

mass number of main impurity

Mass number of the plasma main impurity. Possible values are: 8 (Beryllium), 10 (Boron), 12 (C), etc ... & C

PIMPZ

Real

charge number of main impurity

Charge number of the plasma main impurity. Possible values are: 4 (Beryllium), 5 (Boron), 6(C), etc ... & C

PINJ

Real

power injected by main neutral beam

The injected neutral beam power with beam of (BGASA, BGASZ) that passes into the torus in watts. Zero if no beams are on. Notice total injected neutral beam power is PINJ + PINJ2.
Normal level of accuracy is ASDEX (± 10%), D3D (± 10%), JET (± 6%), JFT2M (± 5%), PBXM (±5%), PDX (± 10%).

PINJ2

Real

power injected by auxiliary neutral beam

The injected neutral beam power from a second source with beam of (BGASA2, BGASZ2) in watts (JET only). Zero if no beams of second source are on.
Normal level of accuracy is JET (± 6%). ASDEX, D3D, JFT2M, PBXM, PDX: Na.

Real

uncorrected loss power

Estimated Loss Power not corrected for charge exchange and unconfined orbit losses in watts.
ASDEX: PL = POHM + PNBI - DWDIA/3 - 2*DWMHD/3
D3D: PL = POHM + PNBI + PECH - DWMHD
JET: PL = POHM + PNBI + PICRH - DWDIA
JFT2M: PL = POHM + PNBI - DWDIA
PBXM: PL = POHM + PNBI - DWMHD
PDX: PL = POHM + PNBI - DWMHD
ASDEX, D3D, JET, JFT2M, PBXM, PDX: Co.

PLH

Real

LH power coupling to plasma

LH power in watts coupled to the plasma. Zero if no LH is applied.

PLTH

Real

loss power with correction for cx and orbit losses

Estimated Loss Power corrected for charge exchange and unconfined orbit losses in Watts, i.e. PLTH = PL - PFLOSS.
ASDEX, D3D, JET, JFT2M, PBXM, PDX: Co.

PNBI

Real

total injected beam power minus shine through

Total injected neutral beam power minus shine through in watts. Zero if no beams are on.
Normal level of accuracy is ASDEX (± 10%),D3D (± 10%), JET (± 10%), JFT2M (<± 10%), PBXM (± 10%), PDX (± 10%).

POHM

Real

Ohmic power

Total ohmic power in watts.

ASDEX:	Determined from max {0, VSURF*IP}, (Ohmic: ± 5% H: ± 50%).
D3D:	Calculated using CB₁₀I_p²RGEO²/(W_Tn_e). B₁₀ is the central visible bremsstrahlung signal. When n_eis determined from the radial (vertical) CO₂chord, C is equal to 1.0310^-19 (9.9210^-20) (± 15%).
JET:	Corrected for inductance effects (± 20%).
JFT2M:	Calculated as VSURF*IP (± 10%).
PBXM:	Calculated as VSURF*IP (± 50%).
PDX:	Calculated using VSURF and IP corrected for inductance effects (± 20%).

PRAD

Real

radiated power

Total radiated power in watts as measured by Bolometer.
Normal level of accuracy is ASDEX (± 20%), D3D (± 15%), JET (± 10 15%), JFT2M (± 10 - 20%), PBXM (± < 25%), PDX (Na).

PUMP

String

Status of divertor pump

Status of divertor pump ('ON' or 'OFF')

Q95

Real

safety factor at 95% poloidal flux

The plasma safety factor from an MHD equilibrium fit evaluated at the flux surface that encloses 95% of the total poloidal flux. For ASDEX Q95 = q_cyl(1 + (AMIN/RGEO)² (1 + 0.5 BEILI2²)) with q_cyl = 10⁷ (BT/IP) (AMIN²/RGEO) (1 + KAPPA²)/2.
Normal level of accuracy is ASDEX (± 15%), D3D (± 3%),JET (± 10%), JFT2M (± 10%) PBXM(±10%), PDX (± 10%).

QAXIS

Real

central safety factor on the magnetic axis

QFOOT

Real

safety factor at an ITB foot

QMIN

Real

Minimum safety factor

RFOOT

Real

&rho corresponding to the ITB foot

&rho corresponding to ITB foot

RGEO

Real

geometric axis

The plasma geometrical major radius in meters, from an MHD equilibrium fit, defined as the average of the minimum and the maximum radial extent of the plasma at the elevation of the magnetic axis.
Normal level of accuracy is ASDEX (± 0.5%), D3D (± 0.6%) JET (± 1%), JFT2M (± 0.75%), PBXM (± 0.65%), PDX (± 0.75%).

RICRES

Real

Normalised minor radius (&rho) of ICRH deposition.

RLHDEP

Real

Normalised minor radius (&rho) of lower hybrid deposition.

RMAG

Real

magnetic axis

The major radius of the magnetic axis in meters from an MHD equilibrium fit or a formula based on a number of equilibria (ASDEX).
Normal level of accuracy is ASDEX (± 0.5%), D3D (± 1%), JET (± 2%), JFT2M (±2%), PBXM (± 1%), PDX (± 4%).

RQMIN

Real

&rho corresponding to the minimum in safety factor, QMIN.

&rho corresponding to the minimum in safety factor, QMIN. ( &rho is the normalised flux surface label proportional to the square root of the toroidal flux )

RSHOULD

Real

&rho corresponding to an ITB shoulder

RSMIN

Real

&rho of the surface with minimum magnetic shear

SELDB

Integer

Sequence of binary flags stored as a 10 digit integer: abcdefghij. These digits carry the following information

a	1 if MSE available in equilibrium reconstruction, 0 otherwise
b	1 if profile data is available, 0 otherwise
c-j	no definitions at present, so set to 0

SEPLIM

Real

minimum separation between separatrix and limiter/wall

The minimum distance between the separatrix flux surface and either the vessel wall or limiters in meters from an MHD equilibrium fit or a formula based on a number of equilibria (ASDEX).
Normal level of accuracy is ASDEX (± 1 cm), D3D (± 0.5 cm), JET (± 1 cm), JFT2M (± 1 cm), PBXM (± 0.5 cm), PDX (± 1 cm).

SFOOT

Real

magnetic shear at ITB foot

magnetic shear (defined as s=&rho/q dq/d&rho where &rho is the square root normalised toroidal flux coordinate) at ITB foot

SHEAR

String

sign of magnetic shear inside ITB radius

General sign of the magnetic shear inside ITB radius with allowed values: "NE", "WE", "PO" for negative, weak and positive shear respectively

SHOT

String

shot #

The shot from which the data are taken.

SPLASMA

m^2

Real

area of outermost magnetic surface

Area of outermost magnetic surface in m² ideally determined from an MHD equilibrium fit, but otherwise from the simple formula:
AREA=4&pi AMIN RGEO ((1+&kappa²)/2))^0.5.

STATE

String

plasma state ('STEADY' or 'TRANS')

Description of the plasma state for the present time slice:

STEADY :	All global paramaters are in steady state
TRANS :	At least one parameter is evolving

TAUDIA

Real

Total diamagnetic energy confinement time.

Total diamagnetic energy confinement time in seconds. TAUDIA=WDIA/(POHM+PNBI+PICRH+PECH+PLH+PIBW-DWDIA)

TAUP

Real

Particle confinement time in s.

Particle (electron) confinement time in s.

TAUTH

Real

thermal energy confinement time

Estimated thermal energy confinement time (WTH/PLTH) in seconds.

TAUTH1

Real

Thermal energy confinement time.

Thermal energy confinement time in seconds.
TAUTH1=WKIN/(POHM+PNBI+PICRH+PECH+PLH+PIBW-DWKIN)
where DWKIN is the time derivative of the stored thermal energy as estimated from kinetic measurements

TAUTOT

Real

total energy confinement time

Estimated total energy confinement time (WTOT/PLTH) in seconds.

TE0

Real

central Te

The electron temperature at the magnetic axis in eV.

ASDEX:	From 16 radial YAG measurements under the same profile assumptions as for TEV (± 10%).
D3D:	Determined by a spline temperature profile fit to the Thomson scattering data (± 10%).
JET:	From ECE temperature profile (± 10%).
JFT2M, PBXM, PDX:	Na.

TE95

Real

electron temperature at 95% poloidal flux surface

TEFOOT

Real

electron temperature at the ITB foot

TESHOULD

Real

electron temperature at the ITB shoulder

TEV

Real

volume averaged electron temperature

Volume average electron temperature in eV.

TI0

Real

central Ti

The ion temperature at the magnetic axis in eV.

D3D:	Determined by a spline temperature profile fit to the charge exchange recombination data (± 10%).
JET:	From Crystal X-ray diagnostic (±10%) or from charge exchange recombination spectroscopy (± 10%).
ASDEX, JFT2M, PBXM, PDX:	Na.

TI95

Real

ion temperature at 95% poloidal flux surface

TIFOOT

Real

ion temperature at the ITB foot

TIME

Real

time

Time during the shot at which the data are taken in seconds.

TISHOULD

Real

ion temperature at the ITB shoulder

TIV

Real

volume averaged ion temperature

Volume average ion temperature in eV.

TOK

String

tokamak

This variable designates which tokamak has supplied the data. For example: ASDEX, D3D, JET, JFT2M, PBXM... (10 ASCII characters).

TRTIME

String

Flag for transient or steady enhanced core confinement modes.

Flag for transient or steady enhanced core confinement modes with allowed values: "SS" where the enhanced core confinement lasts for more than 5 energy confinement times and "TR" where the enhancement is more transient.

UPDATE

Integer

last update YYYYMMDD

The date of the most recent update for any variable listed in the database. The format is YYYYMMDD (Year-Month-Day).

VOL

m^3

Real

plasma volume

The plasmas volume in m³ determined from an MHD equilibrium fit or a formula based on a number of equilibria (ASDEX).
Normal level of accuracy is ASDEX (± 3%), D3D (± 3%),JET (± 6%), JFT2M (± 5%), PBXM (± 10%), PDX (±5%).

VSURF

Real

loop voltage

The loop voltage at the plasma boundary in volts.
Normal level of accuracy is ASDEX (± 5%), D3D (Na),JET (± 5%), JFT2M (± 5%), PBXM (±50%), PDX (± 10%).

VTO95

m/s

Real

Toroidal velocity at 95% poloidal flux surface in m/s.

VTOAXIS

m/s

Real

Toroidal velocity on axis in m/s.

VTOFOOT

m/s

Real

Toroidal velocity at the ITB foot in m/s.

WALMAT

String

wall material

The material of the vessel wall. Possible values are: SS for stainless steel, IN for inconel, IN/C for Inconel with carbon, CSS for (partly) Carbon on stainless steel, or C for generic carbon.

WDIA

Real

Total plasma energy in Joules as determined from the diamagnetic loop.

WFANI

Real

fraction of fast ion energy in perpendicular direction

Estimate of fraction of perpendicular fast ion energy as compared to the totalfast ion energy due to NBI.
If WFPER and WFPAR are available WFANI = WFPER/(WFPER + WFPAR), otherwise:

ASDEX:	From regression analysis based on 176 FREYA runs: C NEL^0.04(NE0(ZEFF-1))^0.045/ENBI^0.14 for H beam and C'NEL^0.12(NE0(ZEFF-1))^0.020/ENBI^0.14 for D beam where C and C' are estimated constants depending on the target gas. Missing central densities are interpolated by regression of the available central densities in the database against IP, BT, NEL, NEV, EVAP and PINJ. If not measured, ZEFF is assumed to be 3 for EVAP=NONE, 2.5 for carbonised shots and 1.5 for boronised shots.
D3D:	The fast ion anisotropy is calculated only from geometry; the angles of the beam center line are known relative to the geometric axis of the tokamak and from this the perpendicular and parallel components can be determined.
JET:	1.16*10^-2NEL^0.11/ENBI^0.07.

Normal level of accuracy is ASDEX (± 7%), D3D (± 50%),JET (± 50%), JFT2M, PBXM, PDX: Co.

WFICRH

Real

perpendicular fast ion energy content during ICRH

Estimate of the perpendicular fast ion energy content during ICRH heating in Joules. It is given by 4/3 (DWDIA - DWMHD), where DWDIA and DWMHD is the increase in energy due to ICRH. Zero if no ICRH.
Normal level of accuracy is JET (± 50%). ASDEX, D3D, JFT2M, PBXM, PDX: Na

WKIN

Real

Total thermal plasma energy in Joules as determined from kinetic measurements.

WMHD

Real

Total plasma energy in Joules as determined from an MHD equilibrium fit.

WTH

Real

thermal plasma energy content

Estimated thermal plasma energy content in Joules.
ASDEX: WTH = WDIA - 1.5*WFANI*WFFORM.
D3D: WTH = WMHD - WFFORM.
JET: WTH = WDIA - 1.5 (WFPER + WFICRH). If WFPER is missing WFPER is replaced by WFANI* WFFORM.
JFT2M: WTH = WDIA/3 + 2*WMHD/3 - WFFORM.
PBXM: WTH = WMHD - 0.75*WFPER - 1.5*WFPAR.
PDX: WTH = WMHD - 0.75*WFPER - 1.5*WFPAR.
ASDEX, D3D, JET, JFT2M, PBXM, PDX: Co.

WTOT

Real

total plasma energy content

Estimated total plasma energy content in Joules.
ASDEX: WTOT = WTH + WFFORM.
D3D: WTOT = WMHD
JET: WTOT = WTH + WFPER + WFPAR + WFICRH.
If WFPER and WFPAR are missing they are replaced by WFFORM.
JFT2M: WTOT = WTH + WFFORM
PBXM: WTOT = WTH + WFPER + WFPAR
PDX: WTOT = WTH + WFPER + WFPAR
ASDEX, D3D, JET, JFT2M, PBXM, PDX: Co.

XPLIM

Real

minimum separation between Xpoint and limiter/wall

The minimum distance between the X-point and either the vessel walls or limiters in meters from an MHD equilibrium fit. The value is positive if X-point is inside either the vessel wall or limiters.
Normal level of accuracy is ASDEX (Na), D3D (± 3 cm), JET (± 5 cm), JFT2M (± 3 cm), PBXM (± 5 cm), PDX (± 5 cm).

ZEFF

Real

line averaged effective charge

Line average plasma effective charge determined from visible bremsstrahlung.
Normal level of accuracy is ASDEX (± 10%), D3D (± 20%), JET (± 30%). JFT2M, PBXM, PDX: Na.

ZMAG

Real

Vertical position of magnetic axis in m

The following quantities were used in the above list but not yet defined, they are not needed for the 0D description:

WFFORM: Total fast ion energy due to NBI in joules estimated from approximate formula. Zero if no NBI is applied.

ASDEX: From regression analysis based on 176 FREYA runs:

CF_TNEL^-1.3 PINJ ENBI^0.75 (WTOT-WFFORM)^0.5 for H beam, and C'F'_T NEL^-1.1 PINJ ENBI (WTOT WFFORM)^0.8for D beam, where C and C' are estimated constants depending on the target gas, and F_T and F'_T are estimated temperature effects. Missing temperature profiles are interpolated by regression of the available YAG temperature profiles in the database against IP, BT, NEL, NEV, EVAP and beam gas.

D3D:

The velocities v_c and v_b are determined from the critical energy and the beam energy respectively, and P_b is the injected neutral beam power. The quantity τ_se is the slowing down-time on electrons first defined by Spitzer,

where A_b and Z_b are the atomic mass and charge of the fast ions, T_e is the electron temperature in eV, n_e is the electron density in m^-3, and logΛ_e=16 is the Coulomb logarithm. If ion drag were negligible, the term in the brackets would be identically one. For DIII-D parameters, however, this term varies rapidly with temperature. To give better agreement with ONETWO results, the above formula is multiplied by 0.55.
JET:0.16*10¹⁹ PINJ/NEV for SHOT #18760, 10¹⁹(0.16 P_80kV+ 0.3 P_140kV + 0.02 P_He)/NEV for SHOT# > 18760.
JFT2M: WFPER + WFPAR.
PBXM: WFPER + WFPAR.
PDX: WFPER + WFPAR.
Normal level of accuracy is ASDEX (± 15%), D3D (± 50%), JET (± 50%), JFT2M, PBXM, PDX: Co.

PFLOSS: Amount of neutral beam power in watts that is lost from the plasma through charge exchange and unconfined orbits.

ASDEX: From fits to FREYA code results, (± 30%)

D3D: PABS exp (3.3 - IP/10⁶)/100 (± 30%).

JET: PINJ exp (3.35 - 0.667|IP|/10⁶- 0.2 NEL/10¹⁹)/100 (± 50%).

JFT2M: From fits to Monte Carlo code results (± 20%).

PBXM: From a fits to the TRANSP code results (± 20%).

PDX: From a fits to the TRANSP code results (± 30%).

OD file formats and examples:

The required format for the 0D description follows the guidelines for the file format adopted to the OD H mode global database and the previous suggested format. The main difference is that the format is extendable to cope with additional variables.

The table below shows the appropriate formats and missing value codes for the three datatypes of 0D variables.

**0D Variables: types, formats, and missing values**
Type	Example 0D Variables	Format	Missing Value
Strings	AUXHEAT, DIVMAT, ECHLOC, TOK, WALMAT etc	A10,1X	????????
Integers	DATE, NM1A, NM1Z, UPDATE etc	I10,1X	-9999999
Reals	AMIN, BT, IP, KAPPA, PNBI, Q95, TE0, ZEFF etc	1PE10.3,1X	-9.999E-09

1X:	One blank space (ASCII code 32).
A10:	10 ASCII characters.
I10:	Integer using up to 10 characters.
1PE10.3:	Floating point number occupying at most 10 characters. Format: ±#.###E±##

0D File Format: CSV (NB Old PR98 style format has been superceded)

The old format for 0D files used in PR98 was quite complex for reading and writing the files.
A much simpler comma separated variable format is used in PR08 with the following benefits

simplify the format of the file
allows creation and viewing from spreadsheets

TOK UPDATE DATE SHOT TIME …

JET 20031201 20001006 53521 1.00E+01 …

JET 20031201 20001006 53521 1.10E+01 …
simplify reading and writing code

The comma separated value (CSV) file format would be one line of header followed by one line per timeslice:

TOK,UPDATE,DATE,SHOT,TIME,…

JET,20031201,20001006,53521,1.00E+01,…

JET,20031201,20001006,53521,1.10E+01,…

The only restriction would be that the strings between the commas should not exceed 10 characters. Padding with spaces is not required between commas.

Example reading and writing routines exist for Fortran, C and IDL.

1D description file: time traces

**PR08 1D Variables**
1D Variable	Units	Data Type	Brief Description	Full Description
AMIN	m	Real	minor radius	The horizontal plasma minor radius in meters from an MHD equilibrium fit or a formula based on a number of equilibria (ASDEX). Normal level of accuracy is ASDEX (± 1%), D3D (± 0.5%),JET (± 3%), JFT2M (± 3%), PBXM (± 3%), PDX (± 3%).
BT	T	Real	vacuum toroidal field at geometric axis	The vacuum toroidal magnetic field in Tesla at RGEO determined from the TF coil current. Positive IP is anti-clockwise when viewed from above. Normal level of accuracy is ± 1% for all machines.
DELTA	-	Real	mean triangularity	The mean triangularity of the plasma boundary from an MHD equilibrium fit. Normal level of accuracy is ASDEX (Na), D3D (± 10%), JET (±10%), JFT2M (± 10%), PBXM (± 25%), PDX (Na).
DELTAL	-	Real	lower triangularity	The lower triangularity of the plasma boundary from an MHD equilibrium fit.
DELTAU	-	Real	upper triangularity	The upper triangularity of the plasma boundary from an MHD equilibrium fit.
IBOOT	A	Real	bootstrap current	Estimated total bootstrap current (in A).
INDENT	m	Real	indentation	Indentation of the plasma determined from an MHD equilibrium fit. Normal level of accuracy is ASDEX (Na), D3D (Na), JET (Na),JFT2M (Na), PBXM (± 15%), PDX (Na).
IP	A	Real	plasma current	The plasma current in amperes determined from an external Rogowski loop with vessel current subtraction. Positive IP is anti-clockwise when viewed from above. Normal level of accuracy is ASDEX (± 2%), D3D (± 1%), JET (± 1%), JFT2M (± 1%), PBXM (± 1%), PDX (± 1%).
KAPPA	-	Real	elongation	The plasma elongation determined from an MHD equilibrium fit or a formula based on a number of equilibria (ASDEX). Normal level of accuracy is ASDEX (± 1%), D3D (± 1%),JET (± 5%), JFT2M (± 10%), PBXM (± 10%),PDX (k = 1 for all records, ±10%).
LI	-	Real	internal inductance	Internal plasma inductance: l_i=2 ∫ B_p²dV / ( μ₀² I_p² R_geo )
NE0	m^-3	Real	central electron density	Central electron density in m^-3.
NEL	m^-3	Real	line averaged electron density	Central line average electron density in m^-3 from interferometer. For JET NEL has been approximated by ohmic: NEL ∝ exp {2.931 +0.873 log (NEV) + 0.064 log (NE0)} H-mode: NEL ∝ exp {3.745 + 0.825 log (NEV) + 0.092 log (NE0)} if no measurement is available. The variable NELFORM indicates if NEL is measured or approximated. Normal level of accuracy is ASDEX (± 2%),D3D (± 2 x 10¹⁸ m^-3),JET (± 8%), JFT2M (± 2%), PBXM (± 5%), PDX(± 5%).
NMAIN0	m^-3	Real	central main ion density	Central main ion density in m-3.
PECH	W	Real	coupled ECH power	ECH power in watts coupled to the plasma. Zero if no ECH is applied. Normal level of accuracy is D3D (± 10%). ASDEX, JET, JFT2M,PBXM, PDX: Na.
PFLOSS	W	Real	lost NBI power	Neutral beam power in watts that is lost from the plasma through charge exchange and unconfined orbits. ASDEX: From fits to FREYA code results, (± 30%) D3D: PABS exp (3.3 - IP/10⁶)/100 (± 30%). JET: PINJ exp (3.35 - 0.667 \| IP \|/10⁶-0.2 NEL/10¹⁹)/100 (± 50%). JFT2M: From fits to Monte Carlo code results (± 20%). PBXM: From a fits to the TRANSP code results (± 20%). PDX: From a fits to the TRANSP code results (± 30%).
PFUSION	W	Real	DT fusion power	Total fusion power due to DT reactions in W.
PHIA	Wb	Real	toroidal flux	Total toroidal flux in Weber enclosed by the plasma
PIBW	W	Real	coupled IBW power	IBW power in watts coupled to the plasma. Zero if no IBW is applied.
PICRH	W	Real	coupled ICRH power	ICRH power in watts coupled to the plasma. Zero if no ICRH is applied. Normal level of accuracy is JET (± 10%). ASDEX, D3D, JFT2M, PBXM, PDX: Na.
PLH	W	Real	coupled LH power	LH power in watts coupled to the plasma. Zero if no LH is applied.
PNBI	W	Real	total injected NBI power	Total injected neutral beam power minus shine through in watts. Zero if no beams are on. Normal level of accuracy is ASDEX (± 10%),D3D (± 10%), JET (± 10%), JFT2M (<± 10%), PBXM (± 10%), PDX (± 10%).
POHM	W	Real	Ohmic power	Total ohmic power in watts. ASDEX: Determined from max {0, VSURFIP}, (Ohmic: ± 5% H: ± 50%). D3D: Calculated using CB₁₀I_p²RGEO²/(W_Tn_e). B₁₀ is the central visible bremsstrahlung signal. When n_eis determined from the radial (vertical) CO₂ chord, C is equal to 1.0310^-19 (9.9210^-20) (± 15%). JET: Corrected for inductance effects (± 20%). JFT2M: Calculated as VSURFIP (± 10%). PBXM: Calculated as VSURF*IP (± 50%). PDX: Calculated using VSURF and IP corrected for inductance effects (± 20%).
PRAD	W	Real	total radiated power	Total radiated power in watts as measured by Bolometer. Normal level of accuracy is ASDEX (± 20%), D3D (±15%), JET (± 10 15%), JFT2M (± 10 - 20%),PBXM (± < 25%), PDX (Na).
Q95	-	Real	safety factor at 95% poloidal flux	The plasma safety factor from an MHD equilibrium fit evaluated at the flux surface that encloses 95% of the total poloidal flux. For ASDEX Q95 = q_cyl(1 + (AMIN/RGEO)²(1 + 0.5 BEILI2²)) with q_cyl = 10⁷ (BT/IP)(AMIN²/RGEO) (1 + KAPPA²)/2. Normal level of accuracy is ASDEX (± 15%), D3D (± 3%), JET (± 10%), JFT2M (± 10%) PBXM (± 10%), PDX (± 10%).
RGEO	m	Real	geometric axis	The plasma geometrical major radius in meters, from an MHD equilibrium fit, defined as the average of the minimum and the maximum radial extent of the plasma. Normal level of accuracy is ASDEX (± 0.5%), D3D (±0.6%) JET (± 1%), JFT2M (± 0.75%),PBXM (± 0.65%), PDX (± 0.75%).
TE0	eV	Real	core electron temperature	The electron temperature at the magnetic axis in eV. ASDEX: From 16 radial YAG measurements under the same profile assumptions as for TEV (± 10%). D3D: Determined by a spline temperature profile fit to the Thomson scattering data (± 10%). JET: From ECE temperature profile (± 10%). JFT2M, PBXM, PDX: Na.
THNT	s^-1	Real	thermal neutron yield	Total thermal neutron yield in s-1.
TI0	eV	Real	core ion temperature	The ion temperature at the magnetic axis in eV. D3D: Determined by a spline temperature profile fit to the charge exchange recombination data (± 10%). JET: From Crystal X-ray diagnostic (±10%) or from charge exchange recombination spectroscopy (± 10%). ASDEX, JFT2M, PBXM, PDX: Na.
VLOOP	V	Real	measured loop voltage	Measured loop voltage at the coil location in
VSURF	V	Real	plasma surface loop voltage	The loop voltage at the plasma boundary in volts. Normal level of accuracy is ASDEX (± 5%), D3D (Na), JET (± 5%), JFT2M (± 5%), PBXM (±50%), PDX (± 10%).
WTH	J	Real	thermal plasma energy content	Estimated thermal plasma energy content in Joules. ASDEX: WTH = WDIA - 1.5WFANIWFFORM. D3D: WTH = WMHD - WFFORM. JET: WTH = WDIA - 1.5 (WFPER + WFICRH). If WFPER is missing WFPER is replaced by WFANI* WFFORM. JFT2M: WTH = WDIA/3 + 2WMHD/3 - WFFORM. PBXM: WTH = WMHD - 0.75WFPER - 1.5WFPAR. PDX: WTH = WMHD - 0.75WFPER - 1.5*WFPAR. ASDEX, D3D, JET, JFT2M, PBXM, PDX: Co.
WTOT	J	Real	total plasma energy content	Estimated total plasma energy content in Joules. ASDEX: WTOT = WTH + WFFORM. D3D: WTOT = WMHD JET: WTOT = WTH + WFPER + WFPAR + WFICRH. If WFPER and WFPAR are missing they are replaced by WFFORM. JFT2M: WTOT = WTH + WFFORM PBXM: WTOT = WTH + WFPER + WFPAR PDX: WTOT = WTH + WFPER + WFPAR ASDEX, D3D, JET, JFT2M, PBXM, PDX: Co.
ZEFF	-	Real	line averaged effective charge	Line average plasma effective charge determined from visible bremsstrahlung. Normal level of accuracy is ASDEX (± 10%),D3D (± 20%). JET (± 30%). JFT2M, PBXM, PDX: Na.

2D description file: Evolving radial profiles

Note that all radial profile should be given using the square root of the normalized toroidal flux as the radial label r.

**PR08 2D Variables**
2D Variable	Units	Data Type	Brief Description	Full Description
BPOL	T	Real	flux surface averaged poloidal magnetic field	Surface averaged poloidal magnetic field in Tesla.
CHIE	m^2/s	Real	estimated electron thermal diffusivity	Estimated thermal electrons heat diffusivity in m2 s-1.
CHII	m^2/s	Real	estimated ion thermal diffusivity	Estimated thermal ions heat diffusivity in m2 s-1.
CURBS	A/m^2	Real	bootstrap current profile	Bootstrap current profile in A m-2. (+ve value indicates anti-clockwise current when viewed from above)
CURECH	A/m^2	Real	ECH driven current profile	Current drive profile by ECH in A m-2. (+ve value indicates anti-clockwise current when viewed from above)
CURICRH	A/m^2	Real	ICRH driven current profile	Current drive profile by ICRH in A m-2. (+ve value indicates anti-clockwise current when viewed from above)
CURLH	A/m^2	Real	LH driven current profile	Current drive profile by LH in A m-2. (+ve value indicates anti-clockwise current when viewed from above)
CURNBI	A/m^2	Real	NBI driven current profile	Current drive profile by beams in A m-2. (+ve value indicates anti-clockwise current when viewed from above)
CURTOT	A/m^2	Real	total current density	Total current density in A m-2. (+ve value indicates anti-clockwise current when viewed from above)
CURTOTEB	A/m^2	Real	error in total current density	Error bars on total current density in A m-2. Provided on same radial positions as CURTOT.
DELTAR	-	Real	mean triangularity	The mean triangularity of the plasma boundary from an MHD equilibrium fit. Normal level of accuracy is ASDEX (Na), D3D (± 10%), JET (±10%), JFT2M (± 10%), PBXM (± 25%), PDX (Na).
DELTARL	-	Real	lower triangularity	The lower triangularity of the plasma boundary from an MHD equilibrium fit.
DELTARU	-	Real	upper triangularity	The upper triangularity of the plasma boundary from an MHD equilibrium fit.
DNER	m^-3/s	Real	time derivative of electron density	Term ∂ n_e(ρ,t) / ∂ t of the electron particles conservation equation in m^-3s^-1.
DWER	W/m^3	Real	time derivative of electron thermal energy density	Term ∂ W_e(ρ,t) / ∂ t of the energy conservation equation in W/m³.
DWIR	W/m^3	Real	time derivative of ion thermal energy density	Term ∂ W_i(ρ,t) / ∂ t of the energy conservation equation in W/m³, where i is the main thermal ion.
GRHO1	m^-1	Real	⟨ \| ∇ ρ \| ⟩	Metric quantity: ⟨ \| ∇ ρ \| ⟩ where ρ is the square root of the normalised toroidal flux
GRHO2	m^-2	Real	⟨ \| ∇ ρ \| ² ⟩	Metric quantity ⟨ \| ∇ ρ \| ² ⟩, where ρ is the square root of the normalised toroidal flux
INDENTR	m	Real	indentation	Averaged indentation of the magnetic surface.
IOTAVAC	-	Real	stellarator (not tokamaks) vacuum rotational transform	Stellarator vacuum rotational transform. Omitted for Tokamaks.
KAPPAR	-	Real	elongation	Average elongation of the magnetic surface.
MOM	Ns/m^2	Real	total toroidal angular momentum density	toroidal angular momentum density. +ve MOM is anti-clockwise when viewed from above
NE	m^-3	Real	interpolated electron density	Fitted electron density profile in m-3.
NEEB	m^-3	Real	error in interpolated electron density	Error bars on the fitted electron density profile in m-3. Provided on the same radial positions as NE.
NEXP	m^-3	Real	experimental electron density	Measured electron density profile in m-3.
NEXPEB	m^-3	Real	error in experimental electron density	Error bars on the measured electron density profile in m-3. NEXPEB is added to NEXP for the upper limit. NEXPEB is subtracted from NEXP for the lower limit. Provided on the same radial positions as NEXP.
NFASTn	m^-3	Real	interpolated nth fast ion density	nth fast ion density profile in m-3. n<9
NHYA	-	Real	mean mass number of hydrogenic ion species	mean mass number of hydrogenic ion species (n_h + 2 n_d + 3 n_t) / (n_h + n_d + n_t)
NM1	m^-3	Real	interpolated main ion density	Main ion density profile in m-3.
NM1EB	m^-3	Real	error in interpolated main ion density	Error bars on main ion density profile in m-3.
NM1XP	m^-3	Real	experimental main ion density	Measured main ion density profile in m-3.
NM1XPEB	m^-3	Real	error in experimental main ion density	Error bars on measured main ion density profile in m-3.
NM2	m^-3	Real	interpolated 2nd main ion density	Secondary main ion density profile in m-3. For instance helium injection into deuterium plasma.
NM2EB	m^-3	Real	error in interpolated 2nd main ion density	Error bars on secondary main ion density profile in m-3.
NM2XP	m^-3	Real	experimental 2nd main ion density	Measured secondary main ion density profile in m-3.
NM2XPEB	m^-3	Real	error in experimental 2nd main ion density	Error bars on measured secondary main ion density profile in m-3.
NM3	m^-3	Real	interpolated 3rd main ion density	Third main ion density profile in m-3. For instance helium injection into deuterium plasma.
NM3EB	m^-3	Real	error in interpolated 3rd main ion density	Error bars on third main ion density profile in m-3.
NM3XP	m^-3	Real	experimental 3rd main ion density	Measured third main ion density profile in m-3.
NM3XPEB	m^-3	Real	error in experimental 3rd main ion density	Error bars on measured third main ion density profile in m-3.
NMn	m^-3	Real	interpolated nth main ion density	nth main ion density profile in m^-3. 1 &le n &le 9. If there are m main ion species, then NM1 - NMm should be filled, and NMm+1 - NM9 should be missing.
NMnEB	m^-3	Real	error in interpolated nth main ion density	Error bars on nth main ion density profile in m-3.
NMnXP	m^-3	Real	experimental nth main ion density	Measured nth main ion density profile in m-3.
NMnXPEB	m^-3	Real	error in experimental nth main ion density	Error bars on measured nth main ion density profile in m-3.
PRES	Pa	Real	scalar MHD pressure profile	scalar MHD pressure flux function, as used in solution of Grad-Shafranov equilibrium equation
Q	-	Real	safety factor profile	Safety factor profile.
QEB	-	Real	error in safety factor profile	Error bars on safety factor profile. Provided on the same radial positions as Q.
QECHE	W/m^3	Real	ECH electron power deposition	Power deposition profile
QECHI	W/m^3	Real	ECH ion power deposition	Power deposition profile on thermal ions by ECH in W/m-3.
QEI	W/m^3	Real	equipartition power density	Equipartition power density from electrons to ions in W m-3.
QFUSE	W/m^3	Real	fusion power deposition to electrons	Electron heating density due to fusion DT reaction in Wm^-3.
QFUSI	W/m^3	Real	fusion power deposition to ions	Main thermal ion heating density due to DT fusion reaction in Wm^-3. Includes the thermalization power (1.5 S_{thermal α} T_i) when Helium⁴ is the main thermal ion.
QIBWE	W/m^3	Real	IBW electron power deposition	Power deposition profile on thermal electrons by IBW in W/m-3.
QIBWI	W/m^3	Real	IBW ion power deposition	Power deposition profile on thermal ions by IBW in W/m-3.
QICRHE	W/m^3	Real	ICRH electron power deposition	Power deposition profile on thermal electrons by icrh in W/m-3.
QICRHI	W/m^3	Real	ICRH ion power deposition	Power deposition profile on thermal ions by icrh in W/m-3.
QLHE	W/m^3	Real	LH electron power deposition	Power deposition profile on thermal electrons by LH in W/m-3.
QLHI	W/m^3	Real	LH ion power deposition	Power deposition profile on thermal ions by LH in W/m-3.
QNBIE	W/m^3	Real	NBI electron power deposition	Power deposition profile on thermal electrons by beams in W/m-3.
QNBII	W/m^3	Real	NBI ion power deposition	Power deposition profile on thermal ions by beams in W/m-3. (includes the thermalization power of fast ions
QOHM	W/m^3	Real	Ohmic power density	Ohmic power density in W m-3.
QRAD	W/m^3	Real	radiated power density	Total radiated power density in W m-3.
QWALLE	W/m^3	Real	electron heat loss from ionisation of wall neutrals	Thermal electrons heat loss due to the ionisation of wall neutrals in W m^-3.
QWALLI	W/m^3	Real	ion heat loss from ionisation/CX of wall neutrals	Main thermal ion heat loss due to ionisation and charge exchange with wall neutrals in Wm^-3. = ⟨ σ v ⟩ _cx n₀ n_i (1.5 T_i - E₀ ) +⟨ σ v ⟩ _ionisation n₀ n_e E₀
RHOxxxx	-	Real	evolving rho grid for experimental data	evolving rho grid for experimental data, where xxxx = TEXP, TEXPEB, TIXP, TIXPEB, NEXP, NEXPEB, NMnXP, NMnXPEB, VROTXP, VROTXPEB (where n labels thermal ion species 1&le n&le 9).
RMAJOR	m	Real	major radius	The geometrical major radius in meters, from an MHD equilibrium fit, defined as the average of the minimum and the maximum radial extent of the magnetic surface at the elevation of the magnetic axis. Normal level of accuracy is ASDEX (± 0.5%), D3D (± 0.6%) JET (± 1%), JFT2M (± 0.75%), PBXM (± 0.65%), PDX (± 0.75%).
RMINOR	m	Real	minor radius	Geometric minor radius of the magnetic surface at the elevation of the magnetic axis in m .
SBE	m^-3 s^-1	Real	direct beam-electron ionization rate	direct beam-electron ionization rate
SBOI	m^-3 s^-1	Real	sink rate of neutrals due to impact ionisation on fast ions	sink rate of neutrals due to impact ionisation on fast ions
SBOX	m^-3 s^-1	Real	sink rate of neutrals due to charge exchange on fast ions	sink rate of neutrals due to charge exchange on fast ions
SNBIE	m^-3/s	Real	NBI electron source	Source of thermal electrons from beams in s-1 m-3.
SNBII	m^-3/s	Real	NBI ion source	Source of thermal ions from beams due to thermalization of beams particle and include charge exchange processes, in s-1 m-3.
SURF	m^2	Real	surface area	Surface area of the magnetic surface in m2.
SWALL	m^-3/s	Real	ion particle source from ionisation of recycled wall neutrals	Main thermal ion particle source term due to ionisation of recycling wall neutrals in m^-3s^-1.
TE	eV	Real	interpolated electron temperature	Fitted electron temperature profile in eV.
TEEB	eV	Real	error in interpolated electron temperature	Error bars on the fitted electron temperature profile in eV. Provided on the same radial positions as TE.
TEXP	eV	Real	experimental electron temperature	Measured electron temperature profile in eV.
TEXPEB	eV	Real	error in experimental electron temperature	Error bars on the measured electron temperature profile in eV.
TI	eV	Real	interpolated ion temperature	Fitted ion temperature profile in eV.
TIEB	eV	Real	error in interpolated ion temperature	Error bars on the fitted ion temperature profile in eV. Provided on the same radial positions as TI.
TIXP	eV	Real	experimental ion temperature	Measured ion temperature profile in eV.
TIXPEB	eV	Real	error in experimental ion temperature	Error bars on the measured ion temperature profile in eV. TIXPEB is added to TIXP for the upper limit. TIXPEB is subtracted from TIXP for the lower limit. Provided on the same radial positions as TIXP.
TORQ	N/m^2	Real	external torque density on plasma	external torque density on plasma. +ve TORQ is anti-clockwise when viewed from above
UBPAR	J m^-3	Real	parallel beam kinetic energy density	parallel beam kinetic energy density
UBPRP	J m^-3	Real	perpendicular beam kinetic energy density	perpendicular beam kinetic energy density
VOLUME	m^3	Real	volume	Volume enclosed by the magnetic surface in m3.
VROT	rad/s	Real	fitted toroidal angular speed	Generic and long-standing variable to store the fitted toroidal angular speed in rad/s. The comments file should specify the ion species that is associated with the submitted data: eg Carbon impurity rotation based on CXRS measurements, or estimated mass weighted average over all ion species of the toroidal angular speed using impurity rotation measurements and a physics model (such as the neoclassical model of NCLASS). +ve VROT is anti-clockwise when viewed from above.
VROTEB	rad/s	Real	error in fitted toroidal angular speed	Error bars on fitted toroidal angular speed in rad/s. Provided on same radial positions as VROT.
VROTM	rad/s	Real	Mass weighted mean toroidal angular speed	Mass weighted mean toroidal angular speed in rad/s. The comments file should specify the measurements and model assumptions used to estimate this data: eg combining impurity rotation measurements of C, O and the neoclassical model of NCLASS and assuming negligible poloidal rotation. +ve VROTM is anti-clockwise when viewed from above.
VROTMEB	rad/s	Real	Error in mass weighted mean toroidal angular speed	Error in mass weighted mean toroidal angular speed (rad/s).
VROTXP	rad/s	Real	experimental toroidal angular speed	Measured toroidal angular speed in rad/s. The comments file should specify the nature of submitted data more precisely: eg fitted Carbon impurity rotation based on CXRS measurements, or an estimate of the mass weighted average toroidal angular speed over all ion species using impurity rotation measurements and a physics model (such as the neoclassical theory model of NCLASS). +ve VROTXP is anti-clockwise when viewed from above.
VROTXPEB	rad/s	Real	error in experimental toroidal angular speed	Error bars on measured toroidal angular speed (rad/s). VROTXPEB is added to VROTXP for upper limit. VROTXPEB is subtracted from VROTXP for lower limit. Provided on same radial positions as VROTXP.
ZEFFR	-	Real	effective charge profile	Plasma effective charge radial profile.
ZEFFREB	-	Real	error in effective charge profile	Error bars on plasma effective charge radial profile. Provided on the same radial positions as ZEFFR.

Index Format for time evolving radial grids

The file format for 2D profiles implies that a fixed radial vector in RHO space be used for each time point given in the time vector. However, experimental data are often measured on a grid (typically the major radius) which does not correspond to a fixed grid when translated in RHO space. In such cases it is not possible to project the measurement grid onto a fixed RHO grid for each time point without significant loss of information. To remedy this problem, an additional level of indirection is introduced: an index is used to label each radial measurement as a function of time, a separate 2D file gives the RHO coordinate for each index as a function of time.

The process can be schematically represented as follows:

Standard 2D format:

RHO vector (rho1, rho2, .... rhoN)

TIME vector: (t1, t2, .... , tM)

DATA vector: (data(rho1,t1),...,data(rhoN,t1), ..., data(rhoN, tM)

Index format:

Data file:

INDEX vector (0, 1, .... N)

TIME vector: (t1, t2, .... , tM)

DATA vector: (data(0,t1),...,data(0,t1), ..., data(N, tM)

RHO file:

INDEX vector (i1, i2, .... iN)

TIME vector: (t1, t2, .... , tM)

RHO vector: (rho(i1,t1),...,rho(iN,t1), ..., rho(iN, tM)

This special format is to be used only for:
* measured quantities that would lose significant information if projected onto a fixed RHO grid as a function of time,
* the following 2D signals:TEXP, TEXPEB, TIXP, TIXPEB, NEXP, NEXPEB, NM1XP, NM1XPEB, NM2XP, NM2XPEB, NM3XP, NM3XPEB, NIMPXP, NIMPXPEB, VROTXP, VROTXPEB. (i.e. experimental measurements and their corresponding error bars)
* The signal name for the RHO vector of the RHO file should be the name of the signal with 'RHO' at the beginning.For instance, experimental data points for TE would have the signal name: TEXP and will be followed by a file with singal name: 'RHOTEXP'

Formats of 1D and 2D files

The 1D and 2D description files are themselves composed of a list of files, one for each of the variables listed above.

The format for the variable files is ASCII UFILE as developed at PPPL by D. McCune.
2D UFILEs should be provided as a function of the square root of the normalized toroidal flux (from 0 at the center to 1 at the edge).

The first independent variable should be the radial vector followed by the time vector:

RHO ;-INDEPENDENT VARIABLE LABEL: X-

TIME SECONDS ;-INDEPENDENT VARIABLE LABEL: Y-

TE ;-DEPENDENT VARIABLE LABEL-

For index file (see VI.d) the vectors are:

INDEX ;-INDEPENDENT VARIABLE LABEL: X-

TIME SECONDS ;-INDEPENDENT VARIABLE LABEL: Y-

TEXP ;-DEPENDENT VARIABLE LABEL-

and a separate set:

INDEX ;-INDEPENDENT VARIABLE LABEL: X-

TIME SECONDS ;-INDEPENDENT VARIABLE LABEL: Y-

RHOTEXP ;-DEPENDENT VARIABLE LABEL-

The radial vector RHO must be sorted in increasing order of the normalized toroidal flux. In order words, it should increase monotonically from the minimum value (closest to the axis) to its maximum value (closest to the edge or even beyond the separatrix if available).

Of course the data vector (containing the dependent variable) should be consistent with the order in which the radial vector is given. Similarly, the INDEX vector should contain integers in increasing order starting from 0.

The field '-DEPENDENT VARIABLE LABEL-' should contain only the name of the variable as it appears in this manual.

For instance:

QNBII ;-DEPENDENT VARIABLE LABEL-

Software information for reading and writing UFILEs and various software for extracting and retrieving the data are provided, whenever available, in: /pub/profile_data/software.

-The various files are assembled together in two single files - one regrouping all 1D Ufiles the other regrouping all 2D Ufiles. UFILEs are separated by two lines of at list 10 '*' (ASCII code 42) as follow:

--- UFILE 1 -----
************************************************
************************************************
--- UFILE 2 -----
************************************************
************************************************
--- UFILE 3 -----

The file containing the separatrix information should be grouped with the 2D UFILEs.

PR08 File naming convention

-The comments file for the discharge (plain ASCII text) is called:

pr08_tok_#####_com.dat

The file containing the 0D data is called:

pr08_tok_#####_0d.dat

The file grouping all 1D files is called:

pr08_tok_#####_1d.dat

The file grouping all 2D files is called:

pr08_tok_#####_2d.dat

The optional files containing all measured experimental data (see section on Index method):

pr08_tok_#####_2dexp.dat

where tok is the name of the Tokamak and ##### is the pulse number.

On the ffp server tokamak-profiledb.ccfe.ac.uk the data corresponding to the tokamak tok , shot number ##### appears in the directory: /itpa_pro8/tok/##### which contains:

pr08_tok_#####_com.dat

pr08_tok_#####_0d.dat

pr08_tok_#####_1d.dat

pr08_tok_#####_2d.dat

PR98 Data now Accessible via MDSplus

Profile Database Access via MDSplus

Profile database data is accessible from `tokamak-profiledb.ccfe.ac.uk' via MDSplus, thanks to Tom Fredian, Josh Stillerman and Martin Greenwald at MIT who have helped with setting up the server and in converting the data.

Documentation on MDSplus for Profile Database:

If you are new to MDSplus, then Tom Fredian's talk is probably the best place to start.

Official MDSplus Documentation: information on installing and using MDSplus
Talk by Tom Fredian Introduction to accessing the Profile Database using MDSplus (Princeton, March 2002).
MDSplus Tree Structure for the Converted Data: MDSplus Profile Database Trees

Example routines to Read/Write MDSplus trees:

Simple IDL Example reading a few database items into an IDL program
IDL procedure to read all profile database data from a given discharge into IDL structures (originally from Martin Greenwald)
Fortran Example reading a few database items into a Fortran program, with the makefile to compile with the Absoft f77 compiler (originally from David Mikkelsen)
MATLAB Example reading a few database items into a MATLAB program (from Frederic Imbeaux)
IDL example to write an MDSplus tree on the tokamak-profiledb.ccfe.ac.uk MDSplus server (Malcolm Walters)
TCL script to generate profile database model tree files (Josh Stillerman):

NB you must first install MDSplus on your machine before running these!

MDSplus Server and Tree Names

If you want to get started, then the following information is crucial.

Database	PR08	PR98	Working DB	ITB DB
MDSplus Server Name	`tokamak-profiledb.ccfe.ac.uk'
Tree Names	pr08_tok⁰	pr98_tok¹	tok¹	itb_tok¹
Read Access	unrestricted	unrestricted	registration required²	registration required²
Write Access	not applicable	not applicable	registration required³	registration required³

⁰ where tok= `aug', `cmod', `d3d', `ftu', `iter', `jet', `jt60u', `mast', `rtp', 't10', 'tftr', 'ts', 'txtr'
¹ where tok= `aug', `cmod', `d3d', `ftu', `jet', `jt60u', `rtp', 't10', 'tftr', 'ts', 'txtr'
² permission must be granted from the appropriate ITPA group.
³ only bona-fide data-providers will be granted write access int the database transit areas

Registration for MDSplus Access to Restricted Databases

MDSplus access to WDB and ITB databases is ONLY possible for registered IP addresses/usernames. PR98 is NOT subject to this restriction. To access the restricted databases (WDB, ITB) via MDSplus, you must register with us the following information:

the username, hostname, and IP address for the machine account from which you want MDSplus access to the profile database
the particular database trees that you want to access: ie wdb or itb

To register simply email your registration details.

Examples of Recent Submissions

See recent database submissions for example file formats:

NB: you need access to the restricted area to get there!

Some Useful Contributed Software

Various Ufile read/write software:

Stan Kaye's FORTRAN and IDL routines to write UFILES from TRANSP could be useful for data providers.
Malcolm Walters FORTRAN routines to read and write more recent and more flexible 0D UFILES (also useful for data providers.)

Various software to read/write MDSplus trees:

Simple IDL Example reading a few database items into an IDL program
IDL procedure to read all profile database data from a given discharge into IDL structures (originally from Martin Greenwald)
Fortran Example reading a few database items into a Fortran program, with the makefile to compile with the Absoft f77 compiler (originally from David Mikkelsen)
MATLAB Example reading a few database items into a MATLAB program (from Frederic Imbeaux)
IDL example to write an MDSplus tree on the tokamak-profiledb.ccfe.ac.uk MDSplus server (Malcolm Walters)
TCL script to generate profile database model tree files (Josh Stillerman):

TOK	UPDATE	DATE	SHOT	TIME	…
JET	20031201	20001006	53521	1.00E+01	…
JET	20031201	20001006	53521	1.10E+01	…