Table Of ContentJUL I 0 2000
SAND2000-1369
Unlimited Release
Printed June 2000
Proceedings of 1999 US/Japan Workshop (99FT-05)
On
High Heat Flux Components and Plasma Surface Interactions
For Next Fusion Devices
Santa FeyN M
-
November 1 4,1999
Edited by
Richard Nygren and Diana Stavros
Fusion Technology Department, 6428
Sandia National Laboratories
P. 0. Box 5800
Albuquerque, New Mexico 8718 5-1 129
Abstract
The 1999 US-Japan Workshop on High Heat Flux Components and Plasma
Surface Interactions in Next Step Fusion devices was held at the St.
Francis Hotel in Santa FeyN ew Mexico, on November 1-4, 1999. There were
42 presentations as well as discussion on technical issues and planning
for future collaborations. The participants included 22 researchers from
Japan and the United States as well as seven researchers from Europe and
Russia.
There have been important changes in the programs in both the US and
Japan in the areas of plasma surface interactions and plasma facing
components. The US has moved away from a strong focus on the ITER
Project and has introduced new programs on use of liquid surfaces for
plasma facing components, and operation of NSTX has begun. In Japan,
the Large Helical Device began operation. This is the first large world-class
confinement device operating in a magnetic configuration different than a
tokamak. In selecting the presentations for this workshop, the organizers
sought a balance between research in laboratory facilities or confinement
devices related to plasma surface interactions and experimental research
in the development of plasma facing components. In discussions about the
workshop itself, the participants affirmed their preference for a setting
where "work-in-progress" could be informally presented and discussed.
DISCLAIMER
This report was .prepared as an account of work sponsored
by an agency of the United States Government. Neither
the United States Government nor any agency thereof, nor
any of their employees, make any warranty, express or
implied, or assumes any legal liability or responsibility for
the accuracy, completeness, or usefulness of any
information, apparatus, product, or process disclosed, or
represents that its use would not infringe privately owned
rights. Reference herein to any specific commercial
product, process, or service by trade name, trademark,
manufacturer, or otherwise does not necessarily constitute
or imply its endorsement, recommendation, or favoring by
the United States Government or any agency thereof. The
views and opinions of authors expressed herein do not
necessarily state or reflect those of the United States
Government or any agency thereof.
DISCLAIMER
Portions of this document may be illegible
in electronic image products. Images are
produced from the best available original
document.
Table of Contents
Page
Plasma Edge Studies - 1 1-1
(Ulrickson)
Helical-Divertor Installation and Its Performance in LHD
[Noda, NIFS] 1-3
Long Pulse Discharges in LHD
r-z
[Noda, NIFS] 1
Negative Transferred-Arc Cleaning: A Method for Roughening
And Removing Surface Contamination from Plasma Facing
Materials
[Castro, LANL] 1-56
Structure of Helical Divertor Plasmas in LHD
[Suzuki, NIFS] 1-64
Particle Balance Modeling for Steady-state Reactors and Its
Application to Recent Observations in LHD
[Hirooka, NIFS] 1-85
Summary of NSTX PFC Activities and Proposal for Liquid
Metal Experiment in CDXU
[Goransen, ORNL; Kaita, PPPL; Nygren, SNLA] 1-92
In-vessel Observation of JT-60U and Its Divertor Modification
[Masaki, JAERI] I- 126
Plasma Edge Studies - 2 11-1
(NYP en)
Recent Results from DiMES
[Wong, GA1 11-3
Long Term Evolution of Graphite Tiles in DIII-D
[W h yte, UCSD] 11-14
W Poloidal Limiter Experiments in TEXTOR-94
[Tanabe, Nagoya U.] 11-52
V
Plasma Surface Interactions - 1 111-1
(Wampler)
Membrane Pumping of Upgraded Helical Divertor at LHD:
Concept and Simulation Experiments
[Livshits, Bonch-Bruyevich U.] 111-3
Wall Pumping in LHD
[Suzuki, NIFS] 111-30
Plasma-lithium Interaction Measurements in PISCES
[Doerner, UCSD] 111-52
Impact of Mixed-Material Deposition on Plasma-Surface
Interaction
[Yoshida, Kyushu U.] 111-68
Deployment of Active Probes & H Sensor in DIII-D
[Bastasz, SNLL] 111-86
Plasma Wall Interactions Observed by Balmer Lines
Emission in TPE
[Tanabe, Nagoya U.] 111- 100
Chemical Sputtering with High flux Ion Beam
[Isobe, Osaka University] 111- 122
Dynamic Target Behaviour due to Ion Bombardment
[Eckstein, IPPP] 111- 137
Retention of Deuterium and Tritium in Alcator C-Mod
[W ampler, SNLA] 111-156
Plasma Surface Interactions - 2 - Cont’d IV-1
(Doyle)
Retention of H in W coated with C
[Haasz, University of Toronto] IV-3
Retention of Hydrogen in TEXTOR Limiters
[Rubel, RIT] IV-22
Critical PWI Issues for Plasma Facing Materials and
Components in ITER-Class Devices
[Federici, ITER] IV-38
vi
Plasma Facing Components - 1 v-1
(Youchison)
Development of HHF Components for the RTOLRC-ITER
Divertor: Recent Results and Further R&D Plans
[Chiocchio, ITER] v-3
Overview of Development of High Heat Flux
[Akiba, JAERrJ v-2 1
HHF Testing of W Brush Armor Mockups
[Nygren, SNLA] v-29
Material Mixing on Tungsten-Coated Plasma Limiters
[Rubel, RIT; Tanabe, Nagoya Univ.] V-36
Heating Test of Reduced Activation Ferritic Steel
F-82H First Wall
[Hatano, JAERI] V-44
-
Plasma Facing Components 2 VI-1
(Wow>
Effects of divertor plasma on the pebble fall for pebble
Divertor concept
[Nishikawa, Osaka U.] VI-3
Experiment of pebble divertor
[Isobe, Osaka University] VI-27
Recent Results and New Opportunities in Thermal
Hydraulics
[Youchison, SNLA] VI-45
Design Issues and Fatigue Lifetime of JET Hypervapotron
Beam Stopping Elements
[Ciric, JET] VI-62
vii
-
Plasma Facing Components 3 VII-1
(Nygren)
Thermal-hydraulics of Sawtooth-finned Cooling Tubes
[AkibaEzato, JAERI] VII-3
Thermal-hydraulic Analysis of FIRE Divertor
[Baxiwong, GA] VII- 12
PFC Armor and Materials VIII-1
Research and Development of Tungsten-Coated
Divertor Plate
[TokunagdYoshida, RIAM; Kubota/Noda, NIFS;
Y. ImamurdKurumaddOku, Ibaraki University;
Sogabe, Toyo; Suzuki, Kawasaki Heavy Industries;
Kato, Nippon; Plochl, Plansee] VIII-3
Evaluation of Integrity for Carbon Divertor Model
Joined with Copper by using Ti Foil
Imamura/Oku/Kurumada/TomotdKawamataI,b araki
University; Kubota/Noda/Motojima, NIFS] VIII-23
High Heat Flux Tests of Carbon Composite for KSTAR
And NSTX
[NygredYouchison, SNLA; MKim, KBSCI; ParWKim,
Daewoo] VIII-28
Development of a Tungsten Alloy Database for APEX
[Zinkle, ORNL] VIII-38
Appendix A: Workshop Agenda A-1
Appendix B: List of Participants and Addresses B-1
Distribution D-1 through D-12
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Plasma Edge Studies 1
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