Detailed OEDGE modeling of core-pedestal fueling in DIII-D

J. D. Elder; S. Lisgo; A. W. Leonard; P. C. Stangeby; J. A. Boedo; B. D. Bray; N. H. Brooks; M. E. Fenstermacher; D. Reiter; D. L. Rudakov; E. A. Unterberg; J. G. Watkins

doi:10.1016/j.jnucmat.2013.01.137

Detailed OEDGE modeling of core-pedestal fueling in DIII-D

J. D. Elder, S. Lisgo, A. W. Leonard, P. C. Stangeby, J. A. Boedo, B. D. Bray, N. H. Brooks, M. E. Fenstermacher, D. Reiter, D. L. Rudakov, E. A. Unterberg, J. G. Watkins

Power Exhaust and Particle Control

Research output: Contribution to journal › Article › peer-review

1 Scopus citations

Abstract

The OEDGE code is used to model core fueling for attached L-mode plasmas and between edge localized modes (ELMs) for attached H-mode plasmas in DIII-D. Empirical plasma reconstruction has been used to determine the plasma conditions in these discharges. EIRENE is used to model the hydrogen recycling. Divertor recycling accounts for 65-100% of the core fueling. The fraction of the total divertor target flux ionized inside the separatrix ranges from 5% to 20%. The fraction of total wall flux ionized inside the separatrix ranges from 20% to 50%. Neutrals originating from wall regions closer to the separatrix are more likely to ionize in the confined plasma. Ionization in the confined plasma is concentrated below the midplane with peaks in the poloidal profiles just above the X-point. Radial core ionization in high density H-mode is peaked strongly near the separatrix.

Original language	English
Pages (from-to)	S651-S654
Journal	Journal of Nuclear Materials
Volume	438
Issue number	SUPPL
DOIs	https://doi.org/10.1016/j.jnucmat.2013.01.137
State	Published - 2013

Funding

This work was supported in part by the US Department of Energy under DE-FC02-04ER54698, DE-FG02-07ER54917, DE-AC52-07NA27344, DE-AC05-00OR22725, and DE-AC04-94AL85000.

Funders	Funder number
U.S. Department of Energy	DE-AC05-00OR22725, DE-AC04-94AL85000, DE-FC02-04ER54698, DE-AC52-07NA27344, DE-FG02-07ER54917

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1016/j.jnucmat.2013.01.137

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title = "Detailed OEDGE modeling of core-pedestal fueling in DIII-D",

abstract = "The OEDGE code is used to model core fueling for attached L-mode plasmas and between edge localized modes (ELMs) for attached H-mode plasmas in DIII-D. Empirical plasma reconstruction has been used to determine the plasma conditions in these discharges. EIRENE is used to model the hydrogen recycling. Divertor recycling accounts for 65-100% of the core fueling. The fraction of the total divertor target flux ionized inside the separatrix ranges from 5% to 20%. The fraction of total wall flux ionized inside the separatrix ranges from 20% to 50%. Neutrals originating from wall regions closer to the separatrix are more likely to ionize in the confined plasma. Ionization in the confined plasma is concentrated below the midplane with peaks in the poloidal profiles just above the X-point. Radial core ionization in high density H-mode is peaked strongly near the separatrix.",

author = "Elder, {J. D.} and S. Lisgo and Leonard, {A. W.} and Stangeby, {P. C.} and Boedo, {J. A.} and Bray, {B. D.} and Brooks, {N. H.} and Fenstermacher, {M. E.} and D. Reiter and Rudakov, {D. L.} and Unterberg, {E. A.} and Watkins, {J. G.}",

year = "2013",

doi = "10.1016/j.jnucmat.2013.01.137",

language = "English",

volume = "438",

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T1 - Detailed OEDGE modeling of core-pedestal fueling in DIII-D

AU - Elder, J. D.

AU - Lisgo, S.

AU - Leonard, A. W.

AU - Stangeby, P. C.

AU - Boedo, J. A.

AU - Bray, B. D.

AU - Brooks, N. H.

AU - Fenstermacher, M. E.

AU - Reiter, D.

AU - Rudakov, D. L.

AU - Unterberg, E. A.

AU - Watkins, J. G.

PY - 2013

Y1 - 2013

N2 - The OEDGE code is used to model core fueling for attached L-mode plasmas and between edge localized modes (ELMs) for attached H-mode plasmas in DIII-D. Empirical plasma reconstruction has been used to determine the plasma conditions in these discharges. EIRENE is used to model the hydrogen recycling. Divertor recycling accounts for 65-100% of the core fueling. The fraction of the total divertor target flux ionized inside the separatrix ranges from 5% to 20%. The fraction of total wall flux ionized inside the separatrix ranges from 20% to 50%. Neutrals originating from wall regions closer to the separatrix are more likely to ionize in the confined plasma. Ionization in the confined plasma is concentrated below the midplane with peaks in the poloidal profiles just above the X-point. Radial core ionization in high density H-mode is peaked strongly near the separatrix.

AB - The OEDGE code is used to model core fueling for attached L-mode plasmas and between edge localized modes (ELMs) for attached H-mode plasmas in DIII-D. Empirical plasma reconstruction has been used to determine the plasma conditions in these discharges. EIRENE is used to model the hydrogen recycling. Divertor recycling accounts for 65-100% of the core fueling. The fraction of the total divertor target flux ionized inside the separatrix ranges from 5% to 20%. The fraction of total wall flux ionized inside the separatrix ranges from 20% to 50%. Neutrals originating from wall regions closer to the separatrix are more likely to ionize in the confined plasma. Ionization in the confined plasma is concentrated below the midplane with peaks in the poloidal profiles just above the X-point. Radial core ionization in high density H-mode is peaked strongly near the separatrix.

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DO - 10.1016/j.jnucmat.2013.01.137

M3 - Article

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SN - 0022-3115

VL - 438

SP - S651-S654

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - SUPPL

ER -

Detailed OEDGE modeling of core-pedestal fueling in DIII-D

Abstract

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UN SDGs

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