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Title: HEAT simulation and IR data comparison for ST40 plasma-facing components

Journal Article · · Nuclear Materials and Energy

Not Available

Sponsoring Organization:
USDOE
Grant/Contract Number:
AC05-00OR22725
OSTI ID:
2478174
Journal Information:
Nuclear Materials and Energy, Journal Name: Nuclear Materials and Energy Journal Issue: C Vol. 41; ISSN 2352-1791
Publisher:
ElsevierCopyright Statement
Country of Publication:
Netherlands
Language:
English

References (20)

Design optimization of the ITER tungsten divertor vertical targets journal February 2018
Plasma operation with an all metal first-wall: Comparison of an ITER-like wall with a carbon wall in JET journal July 2013
Ion orbit modelling of ELM heat loads on ITER divertor vertical targets journal August 2017
Experimental observations of bifurcated power decay lengths in the near Scrape-Off Layer of ST40 High Field Spherical Tokamak journal December 2024
Inferring the scrape-off layer heat flux width in a divertor with a low degree of axisymmetry journal December 2024
Thermal damage of tungsten-armored plasma-facing components under high heat flux loads journal January 2020
A tensorial approach to computational continuum mechanics using object-oriented techniques journal January 1998
Edge-localized-modes in tokamaks journal September 2014
Feedback system for divertor impurity seeding based on real-time measurements of surface heat flux in the Alcator C-Mod tokamak journal February 2016
A Software Package for Plasma-Facing Component Analysis and Design: The Heat Flux Engineering Analysis Toolkit (HEAT) journal January 2022
Reconstruction of current profile parameters and plasma shapes in tokamaks journal November 1985
High resolution numerical studies of separatrix splitting due to non-axisymmetric perturbation in DIII-D journal April 2009
Effects of transient heating events on tungsten plasma-facing materials in a steady-state divertor-plasma environment* journal April 2011
Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER journal August 2013
High-resolution heat flux width measurements at reactor-level magnetic fields and observation of a unified width scaling across confinement regimes in the Alcator C-Mod tokamak journal July 2018
Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation journal February 2022
3D ion gyro-orbit heat load predictions for NSTX-U journal September 2022
Achievement of ion temperatures in excess of 100 million degrees Kelvin in the compact high-field spherical tokamak ST40 journal March 2023
Characterisation of detachment in the MAST-U Super-X divertor using multi-wavelength imaging of 2D atomic and molecular emission processes journal March 2023
Simulation of Liquid Lithium Divertor Geometry Using SOLPS-ITER journal January 2022

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