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第15回 ITPA（SOL/DIV）の概要
大阪大学 大学院工学研究科 上田良夫
PWI 合同研究会
平成23年 7月20日- 22日
筑波大学プラズマ研究センターシンポジューム
プラズマ物理クラスター スクレープオフ層とダイバー タ物理サブクラスター(第1回会合)
炉工学クラスター ブランケット サブクラスター(第2回会合)
双方向型共同研究会合「ガンマ１０装置における炉壁材料の損耗・再堆積の研究とそのダイバータ開発戦略における位置づけ」

会合概要
 日程
 2011年 5月16日（月）-19日（木） 開催地
 Dipoli Center, VTT (Helsinki, Finland) 参加者数：63名（48名）括弧内は前回の参加者数
 日本からの参加者（敬称略）：芦川、増崎（NIFS）、仲野（JAEA）、上田（阪大）、吉田（九大）

 次回の予定：16th DivSOL ITPA meeting Date : January 16 – 19 (2012)
 Location : Jülich (Germany) Host : FZJ2

May 16, 2011

Agenda of 15th SOL/DIV meeting

1 Fuel retention （報告：芦川）MDsimulations

what can MD bring to PWI modelling ?
MD simulations of PWI at ASIPP
Hydrogen transport in tungsten
The Interaction of H/T with Be and C from Density Functional Theory calculation- Formation of mixed Be/C materials
Hydrogen retention in W - A Multiscale Approach
MD simulation of H and He defects in W
Modeling tungsten surfaces exposed to low-energy He/H plasmas
on extended time scales (beyond MD)

2 Fuel removal （報告：芦川）Be flash heating
W flash heating
D reabsorption by depleted codeposits
deuterium retention in neutron-irradiated tungsten
3 Fuel retention R&D

4 Dust（報告：芦川）Introduction
Dust ejection experiment using sphere carbon dust with different diameters in LHD
First results of a new dust campaign at TEXTOR / DIIID
Large size high velocity dust observed in KSTAR + First experiment in TReD device(Transport and Removal Experiment of Dust) Modification of CDG for dust detection
dust generation in T-10 and QSPA + Dust immobilization in tokamaks
Dust investigations in AUG (collection, classification,comparison to lab measurements)

May 17, 2011
5 Heat flux （報告：増崎）A. Steady state heat
Introduction
flux experiment
TS analysis
JET analysis
Summary of US effort, DIII-D, C-mod and NSTX
Discussion
B. Steady state heat
Chair R. Pitts
flux theory
Theory review
An Heuristic Drift-Based Model of the Power Scrape-Off Width in H-Mode Tokamaks
SOL current contribution to heat flux
Discussion
C. ELM heat flux
Chair R. Pitts
DIII-D analysis
Impact of ELM mitigation with RMPs in AUG on edge parameters
Discussion
D. Detachment
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Chair T. Leonardmodeling
Validation of detached L-mode plasmas in DIII-D, AUG, and JET with UEDGE".
SOLPS grid
SOL current contribution to heat flux
Discussion
7Heat flux R&DDiscussion
8 Fuel retention in gaps （報告：増崎）Tritium retention in gaps of the tile in JT-60U
Erosion/deposition, and retention in gaps in KSTAR.
Studies of hydrocarbon cracking and transport into gaps in TJ-IIMay 18, 2011
9 Material migration （報告：上田）Main chamber
Introduction
migration
intended presentation on modelling of ITER wall erosion/deposition
medium scale modelling of ITER main chamber eorison/redeposition
WallDYN applied to JET
13C injection experiments in AUG and their modeling using DIVIMP and ASCOT, withthe focus on the main chamberLong term tracer experiments for erosion / redeposition pattern on the first wall
Discussion
10 Be erosion （報告：上田）
New data on Be erosion obtained with QSPA plasma guns at ITER-like ELMs
simulations
Erosion/deposition balance in Be seeded high flux D discharges
Discussion
11Material migration R&D
Discussion
12 W damage （報告：上田）Transient heat load tests on monolithic tungsten with high repetition rates W melt experiments in tokamaks W melting and melt layer motion experiments in Pilot-PSI Melting of tungsten sample and metal first wall in LHD tungsten recristallization after melting/erosion
13W R&DDiscussion

May 19, 201116 General modeling review
Improved modeling of prompt redeposition by magnetic pre-sheath forces.
Integrated SOLPS5.0-ERO modeling of carbon migration in the outer divertor ofASDEX Upgrade
W modelling in SOLPS
Discussion
17 Plans for new experimental thrusts
ILW plans →報告（上田）Status and plan of material related experiments on EAST
preliminary results from the SOL measurements in the KSTAR machine including theplan for next campaignDiscussion