skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Plasma power recycling at the divertor surface

Journal Article · · Fusion Science and Technology
DOI:https://doi.org/10.13182/FST16-119· OSTI ID:1338797
 [1];  [1]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

With a divertor made of solid materials like carbon and tungsten, plasma ions are expected to be recycled at the divertor surface with a time-averaged particle recycling coefficient very close to unity in steady-state operation. This means that almost every plasma ion (hydrogen and helium) will be returned to the plasma, mostly as neutrals. The power flux deposited by the plasma on the divertor surface, on the other hand, can have varying recycling characteristics depending on the material choice of the divertor; the run-time atomic composition of the surface, which can be modified by material mix due to impurity migration in the chamber; and the surface morphology change over time. In general, a high-Z–material (such as tungsten) surface tends to reflect light ions and produce stronger power recycling, while a low-Z–material (such as carbon) surface tends to have a larger sticking coefficient for light ions and hence lower power recycling. Here, an explicit constraint on target plasma density and temperature is derived from the truncated bi-Maxwellian sheath model, in relation to the absorbed power load and power recycling coefficient at the divertor surface. Lastly, it is shown that because of the surface recombination energy flux, the attached plasma has a sharper response to power recycling in comparison to a detached plasma.

Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
USDOE Office of Science (SC). Fusion Energy Sciences (FES) (SC-24)
Grant/Contract Number:
AC52-06NA25396
OSTI ID:
1338797
Report Number(s):
LA-UR-16-21594; TRN: US1701180
Journal Information:
Fusion Science and Technology, Vol. 71, Issue 1; ISSN 1536-1055
Publisher:
American Nuclear SocietyCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 1 work
Citation information provided by
Web of Science

References (31)

Plasma-surface interaction in the Be/W environment: Conclusions drawn from the JET-ILW for ITER journal August 2015
Sheath energy transmission in a collisional plasma with collisionless sheath journal October 2015
Surface modifications of W divertor components for EAST during exposure to high heat loads with He journal August 2015
The snowflake divertor journal November 2015
The super X divertor (SXD) and a compact fusion neutron source (CFNS) journal February 2010
The Chodura sheath for angles of a few degrees between the magnetic field and the surface of divertor targets and limiters journal July 2012
Overview on plasma operation with a full tungsten wall in ASDEX Upgrade journal July 2013
High confinement/high radiated power H-mode experiments in Alcator C-Mod and consequences for International Thermonuclear Experimental Reactor (ITER) Q DT  = 10 operation journal May 2011
Experimental studies and modeling of complete H-mode divertor detachment in ASDEX Upgrade journal August 2015
Plasma sheath transmission factors for tokamak edge plasmas journal January 1984
High density operation for reactor-relevant power exhaust journal August 2015
First nitrogen-seeding experiments in JET with the ITER-like Wall journal July 2013
SRIM – The stopping and range of ions in matter (2010)
  • Ziegler, James F.; Ziegler, M. D.; Biersack, J. P.
  • Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 268, Issue 11-12 https://doi.org/10.1016/j.nimb.2010.02.091
journal June 2010
Kinetic simulations of the Chodura and Debye sheaths for magnetic fields with grazing incidence journal January 2016
Reflection and implantation of low energy helium with tungsten surfaces journal April 2014
The Multi-Fluid Codes Edgeid and Edge2D: Models and Results journal January 1992
The Plasma Boundary of Magnetic Fusion Devices book January 2000
Plasma surface interactions in impurity seeded plasmas journal August 2011
Critical role of electron heat flux on Bohm criterion journal December 2016
Modelling of plasma-edge and plasma–wall interaction physics at JET with the metallic first-wall journal February 2016
Impurity seeding in ITER DT plasmas in a carbon-free environment journal August 2015
A fully implicit, time dependent 2-D fluid code for modeling tokamak edge plasmas journal December 1992
Molecular dynamics simulation of low-energy atomic hydrogen on tungsten surface journal December 2010
Sensitivity of the Boundary Plasma to the Plasma-Material Interface journal January 2017
Plasma-material interactions in current tokamaks and their implications for next step fusion reactors journal December 2001
Plasma Edge Physics with B2-Eirene journal February 2006
Investigation of He–W interactions using DiMES on DIII-D journal January 2016
On the Minimum Size of DEMO journal October 2010
The Plasma Boundary of Magnetic Fusion Devices journal January 2001
Plasma Physics and Fusion Energy journal November 2008
Plasma Physics and Fusion Energy journal November 2008

Similar Records

Analysis of noble gas recycling at a fusion plasma divertor
Journal Article · Sat Jun 01 00:00:00 EDT 1996 · Physics of Plasmas · OSTI ID:1338797

The plasma–sheath transition and Bohm criterion in a high recycling divertor
Journal Article · Tue Jun 06 00:00:00 EDT 2023 · Physics of Plasmas · OSTI ID:1338797

Fluid-particle hybrid simulation on the transports of plasma, recycling neutrals, and carbon impurities in the Korea Superconducting Tokamak Advanced Research divertor region
Journal Article · Wed Jun 15 00:00:00 EDT 2005 · Physics of Plasmas · OSTI ID:1338797