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Design and analysis of actively-cooled, edge-transport diagnostic for long-pulsed operation in WEST

Conference ·
 [1];  [1];  [1];  [1];  [1]
  1. ORNL
+ Show Author Affiliations
Next step fusion devices that will operate in steady-state will require complex plasma-facing components (PFCs) that can survive the harsh environment over long timescales not common in current devices. This will require robust plasma facing surfaces that are integrated with active cooling systems. In a collaboration between CEA and ORNL, a plasma-interacting diagnostic is being designed for the W Environment in Steady-state Tokamak (WEST) in Cadarache, France which requires plasma-facing protection like those needed for steady-state PFCs. This integrated diagnostic studies edge transport and impurity migration within WEST, and is planned to include imbedded temperature Langmuir probe sensors, as well as removeable sample slots for ex-situ surface analysis of plasma-material interactions. The entire assembly is expected to move into the plasma edge for periods up to 1000 s having an energy removeable capability of ∼6 kW and seeing a peak heat flux of more than 7 MW/m2. The assembly compliments WEST high fluence campaigns that plan for multiple 1000 s pulses. Within these specifications, the assembly will require a refractory metal plasma facing surface and integral cooling in order to function within the limited space allotted for such diagnostics. Because of the limited space and linear actuator needs, additive manufacturing of the high heat flux working end of the assembly is being considered which could allow for precision cooling-channels and lighter weight designs. Conceptual design along with simulation and analysis results will be presented for this complex diagnostic with novel PFCs.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE; USDOE Office of Science (SC)
DOE Contract Number:
AC05-00OR22725
OSTI ID:
2438961
Country of Publication:
United States
Language:
English

References (8)

A Software Package for Plasma-Facing Component Analysis and Design: The Heat Flux Engineering Analysis Toolkit (HEAT) journal January 2022
3D ion gyro-orbit heat load predictions for NSTX-U journal September 2022
Challenges for plasma-facing components in nuclear fusion journal September 2019
Controlled irradiation of CFC samples in the scrape-off layer of Tore Supra journal March 2005
Electric Probes in Tokamaks: Experience in Tore Supra journal March 2011
HADES - high heat load testing - facility at CEA-IRFM journal July 2023
Acceptance tests of the industrial series manufacturing of WEST ITER-like tungsten actively cooled divertor journal September 2021
Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation journal February 2022

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