Published July 2007 | Version v1
Journal article

Development of integrated SOL/divertor code and simulation study of the JT-60U/JT-60SA tokamaks

  • 1. Japan Atomic Energy Agency, Mukoyama, Naka, Ibaraki 311-0193 (Japan)

Description

To predict the heat and particle controllability in the divertor of tokamak reactors and to optimize the divertor design, comprehensive simulations by integrated modeling allowing for various physical processes are indispensable. SOL/divertor codes have been developed in the Japan Atomic Energy Agency for the interpretation and the prediction of behaviour of SOL/divertor plasmas, neutrals and impurities. The code system consists of the two-dimensional fluid code SOLDOR, the neutral Monte-Carlo (MC) code NEUT2D and the impurity MC code IMPMC. Their integration code 'SONIC' is almost completed and examined to simulate self-consistently the SOL/divertor plasmas in JT-60U. In order to establish the physics modelling used in fluid simulations, the particle simulation code PARASOL has also been developed. Simulation studies using those codes have progressed with the analysis of JT-60U experiments and the divertor designing of JT-60SA (modification program of JT-60U). The X-point multifaceted asymmetric radiation from the edge in the JT-60U experiment is simulated. It is found that the deep penetration of chemically sputtered carbon at the dome causes the large radiation peaking near the X-point. The pumping capability of JT-60SA is evaluated through the simulation. A guideline to enhance the pumping efficiency is obtained in terms of the exhaust slot width and the strike point distance. Transient behaviour of SOL/divertor plasmas after an ELM crash is characterized by the PARASOL simulation; the fast-time-scale heat transport is affected by collisions while the slow-time-scale behaviour is affected by the recycling

Additional details

Identifiers

DOI
10.1088/0741-3335/49/7/S05;
PII
S0741-3335(07)34848-3;

Publishing Information

Journal Title
Plasma Physics and Controlled Fusion
Journal Volume
49
Journal Issue
7
Journal Page Range
p. S77-S85
ISSN
0741-3335
CODEN
PPCFET

Conference

Title
IEA large tokamak IA workshop on edge transport in fusion plasmas
Dates
11-13 Sep 2006
Place
Cracow (Poland)