FusionPapers
図版検索トレンドwiki日本の研究
© 2026 FUSIONPAPERS
About法務情報
トップに戻る

First principle-based multi-channel integrated modelling in support of the design of the Divertor Tokamak Test facility

I. Casiraghi, P. Mantica, F. Koechl, R. Ambrosino, B. Baiocchi, A. Castaldo, J. Citrin, M. Dicorato, L. Frassinetti, A. Mariani2021年被引用 25Nuclear FusionIF 3出版社

An intensive integrated modelling work of the main scenarios of the new Divertor Tokamak Test (DTT) facility with a single null divertor configuration has been performed using first principle quasi-linear transport models, in support of the design of the device and of the definition of its scientific work programme. First results of this integrated modelling work on DTT (R0 = 2.14 m, a = 0.65 m) are presented here along with outcome of the gyrokinetic simulations used to validate the reduced models in the DTT range of parameters. As a result of this work, the heating mix has been defined, the size of device has been increased to R0 = 2.19 m and a = 0.70 m, the use of pellets for fuelling has been recommended and reference profiles for diagnostic design, estimates of neutron yields and fast particle losses have been made available.

日本語訳

単一ヌル・ダイバータ配位を有する新型ダイバータ・トカマク試験装置(DTT)の主要シナリオに関する集中的な統合モデリング研究が、装置設計とその科学的作業計画の策定を支援するために、第一原理準線形輸送モデルを用いて実施された。DTT(R0 = 2.14 m、a = 0.65 m)に関するこの統合モデリング研究の最初の結果は、DTTパラメータ領域における縮約モデルを検証するために用いられたジャイロ運動論的シミュレーションの結果とともに、ここに示される。この研究の結果として、加熱構成が決定され、装置サイズがR0 = 2.19 m、a = 0.70 mに拡大され、燃料供給用ペレットの使用が推奨され、ダイバータ設計のための参照プロファイル、中性子生成量の推定、高速粒子損失が利用可能となった。

wiki

Divertor
この論文にはまだAI要約がありません。

関連論文

Core integrated simulations for the Divertor Tokamak Test facility scenarios towards consistent core-pedestal-SOL modelling

2023Plasma Physics and Controlled Fusion

Time-dependent full-radius integrated modeling of the DTT tokamak main plasma scenarios

2025Nuclear Fusion

Physics basis for the divertor tokamak test facility

2024Nuclear Fusion

Integrated core-SOL modelling of fuelling, density control and divertor heat loads for the flat-top phase of the ITER H-mode D-T plasma scenarios

2019Nuclear Fusion

DTT: a divertor tokamak test facility for the study of the power exhaust issues in view of DEMO

2017Nuclear Fusion

Tokamak divertor plasma emulation with machine learning

2024Nuclear Fusion

Requirements and interface management for the divertor system design and integration in the Divertor Tokamak Test (DTT) facility

2021Fusion Engineering and Design

Preliminary integrated core-SOL-divertor modelling for DTT tokamak with liquid metal divertor targets

2019Fusion Engineering and Design

EAST alternative magnetic configurations: modelling and first experiments

2015Nuclear Fusion

Application of Gaussian process regression to plasma turbulent transport model validation via integrated modelling

2019Nuclear Fusion