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Polevoi, A. R.*; Loarte, A.*; 林 伸彦; Kim, H. S.*; Kim, S. H.*; Koechl, F.*; Kukushkin, A. S.*; Leonov, V. M.*; Medvedev, S. Yu.*; 村上 匡且*; et al.
Nuclear Fusion, 55(6), p.063019_1 - 063019_8, 2015/05
被引用回数：33 パーセンタイル：84.74(Physics, Fluids & Plasmas)The operational space (
-
) for long pulse scenarios of ITER was assessed by 1.5D core transport modelling with pedestal parameters predicted by the EPED1 code. The analyses include the majority of transport models presently used for interpretation of experiments and ITER predictions. The EPED1 code was modified to take into account boundary conditions predicted by SOLPS for ITER. In contrast with standard EPED1 assumptions, EPED1 with the SOLPS boundary conditions predicts no degradation of the pedestal pressure as density is reduced. Lowering the plasma density to 
5-6 
10
m
leads to an increased plasma temperature (similar pedestal pressure), which reduces the loop voltage and increases the duration of the burn phase to 
1000 s with Q 
5 for 
13 MA at moderate normalised pressure (
2). These ITER plasmas require the same level of additional heating power as the reference Q = 10 inductive scenario at 15 MA. However, unlike the "hybrid" scenarios considered previously, these H-mode plasmas do not require specially shaped q profiles nor improved confinement in the core for the transport models considered in this study. Thus, these medium density H-mode plasma scenarios with 13 MA present an attractive alternative to hybrid scenarios to achieve ITER's long pulse Q 5 and deserve further analysis and experimental demonstration in present tokamaks.
Garcia, J.*; 林 伸彦; Baiocchi, B.*; Giruzzi, G.*; 本多 充; 井手 俊介; Maget, P.*; 成田 絵美*; Schneider, M.*; 浦野 創; et al.
Nuclear Fusion, 54(9), p.093010_1 - 093010_13, 2014/09
被引用回数：38 パーセンタイル：86.63(Physics, Fluids & Plasmas)Extensive physics analysis and modelling has been undertaken for the typical operational regimes of the tokamak devices JET and JT-60U with the aim of extrapolating present day experiments to JT-60SA, which shares important characteristics with both tokamaks. A series of representative discharges of two operational scenarios, H-mode and hybrid, have been used for this purpose. Predictive simulations of core turbulence, particle transport, current diffusion and pedestal pressure have been carried out with different combinations of models. The ability of the models for reproducing the experimental data is analysed and scenario calculations for JT-60SA are performed following an optimum set of models.
岩井 保則; 山西 敏彦; 西 正孝
JAERI-Tech 2001-027, 29 Pages, 2001/03
JAERI-Tech-2001-027.pdf:1.11MB
核融合実験炉ITER-FEAT設計作業の一環として、先に設計されたITERの規模縮小に基づく処理流量の減少に対応した水素同位体分離システム(ISS)の概念設計の予備的検討を行った。ISSには三種類のガス流が供給され、深冷蒸留法により高純度トリチウムガス流,高純度重水素ガス流及び軽水素ガス流が生み出される。本報ではシステムの簡略化とITER-FEATの運転シナリオを考慮し、4塔からなる独自の塔構成にISSを提案した。ISS内の最大トリチウムインベントリーについては、運転条件に対応して定まるペレット用のトリチウム濃縮流の検討の進展による低減の可能性を見いだした。また現状の塔構成では環境に排出する軽水素排ガス中のトリチウム濃度がISS運転中に加わるわずかな流量変動によって容易に変動する可能性を指摘し、この流れに対する2塔システムの対策を提案した。
仲里 敏子*; 溝口 忠憲*; 下村 安夫; 杉原 正芳; 常松 俊秀
JAERI-M 91-209, 38 Pages, 1991/12
ITER(国際熱核融合実験炉)の設計パラメータと運転性能についてシステム解析を行なった。ITERの自己点火運転の能力は新しく導出されたITER89Lモード則に対しても、従来の各種Lモード則とほぼ同程度であることが確認された。また新しく導出されたHモード則に対しても同様の評価を行なったところ十分な自己点火性能を有することが確認された。ハイブリッド長パルスおよび定常運転に対しては、壁負荷が高い時にはベータ限界が制限条件となり、またダイバータ条件(熱負荷など)が最も厳しい制限条件であることが示された。これらの制限条件を緩和する可能性として中間Zの不純物混入とトロイダル磁場増大の二つの方法が調べられ、それぞれ有効であることが示された。
苫米地 顕; 藤沢 登; 飯田 浩正; 杉原 正芳; 関 昌弘; 本多 力*; 笠井 雅夫*; 沢田 芳夫*; 小林 武司*; 伊藤 裕*; et al.
JAERI-M 85-083, 403 Pages, 1985/07
この報告書はIAEA主催のINTORワークショップ、フェーズIIA、パート2の日本のナショナル・レポートの第XI、XII、XIII章に相当するものである。本フューズでは、幾つかの重要技術課題の検討及び科学的、技術的データベースの評価を行った。その結果INTORの設計をアップグレードするための修正が必要となった。主要な修正点は、プラズマのべー夕値、運転シナリオ、炉寸法の縮少、中性子フルーエンス、トリチウム生産ブランケット、プラズマ位置制御コイルの組込みに関するものである。上記の章に於いて炉概念修正の経緯及び修正後の設計概要について述べる。
竹田 辰興; 荘司 昭朗; 山本 新; 鈴木 紀男; 滝塚 知典; 溝口 忠憲*; 永見 正幸; 川端 一男*; 杉原 正芳; 藤沢 登
JAERI-M 85-080, 70 Pages, 1985/07
この報告書はIAEA主催のINTORワークショップ、フェーズIIA、パー卜2の日本のナショナルレポートの第VIII章に相当するものである。安定限界、閉込め、中性粒子入射加熱と電流駆動、運転シナリオ、燃焼プラズマに関するデータベースの評価を行なった。R&DプログラムとINTOR設計へのインパクトについても考察した。
Garzotti, L.*; Barbato, E.*; Garcia, J.*; Romanelli, M.*; Stankiewicz, R.*; 林 伸彦; 吉田 麻衣子
no journal, ,
JT-60SA scenarios have been simulated with different codes and transport models. Aim of the simulations was to assess stationary conditions estimated with 0-dimensional codes and provide a profile database for further physics studies. Three scenarios considered are standard H-mode, hybrid, advanced steady-state. Codes deployed are ASTRA, CRONOS, JINTRAC. Core transport models used are TGLF (CRONOS), CDBM (CRONOS), GLF23 (ASTRA, CRONOS), Bohm/gyro-Bohm (ASTRA, JINTRAC). Edge transport barrier models are continuous ELMs (JINTRAC), Cordey scaling + EPED1 (CRONOS). Boundary conditions are imposed at separatrix (CRONOS JINTRAC) or top of the pedestal (ASTRA). Fully predictive simulations of current density, ion density (CRONOS and JINTRAC, density not evolved in ASTRA), ion and electron temperature. No rotation. Equilibrium solver SPIDER or three moments (ASTRA), HELENA (CRONOS) and ESCO (JINTRAC). Results are close to those obtained with zero-dimensional codes. Detail of the profiles differ from code to code. Electron and ion temperatures assumed in zero-dimensional calculations seem to be optimistic for most scenarios. For all scenarios normalized pedestal pressure seems to be below MHD stability limit. Further analysis of pedestal stability is required. Analysis of time dependent scenarios (density and current ramp up and down) is planned.
林 伸彦; Garcia, J.*; 本多 充; 清水 勝宏; 星野 一生; 井手 俊介; Giruzzi, G.*; 坂本 宜照; 鈴木 隆博; 浦野 創
no journal, ,
Development of plasma operation scenarios in JT-60SA has been progressing by using integrated modeling codes. In order to obtain an optimum set of models for the prediction, models are validated by using JT-60U and JET experimental data, and verified by integrated codes such as TOPICS and CRONOS. Predictive simulations are performed to assess the performance of each scenario and to develop optimum scenarios. In the scenario development, various physics aspects are studied by using various types of integrated modeling. The integrated divertor code SONIC showed that Ar seeding can reduce the heat flux on divertor plates below the preferable level (10 MW/m
) with keeping low separatrix density in the full non-inductive current drive scenario, however, there are some amounts of Ar influx to core region. We integrate TOPICS with a core impurity transport code IMPACT and study the Ar accumulation in the core and its effect on the performance. Other studies with integrated modeling will be also presented.
林 伸彦; Garcia, J.*; 本多 充; 清水 勝宏; 星野 一生; 井手 俊介; Giruzzi, G.*; 坂本 宜照; 鈴木 隆博; 浦野 創
no journal, ,
Development of plasma operation scenarios in JT-60SA has been progressing by using integrated modeling codes. Anomalous heat transport model, which are one of major uncertainties in the prediction, have been validated for ITB plasmas with full current drive (CD) condition in JT-60U and JET, and integrated codes TOPICS and CRONOS equipped with the models are used for the model verification. It is found that CDBM model predicts temperatures close to those in experiments or underestimates them, and thus can be used for the conservative prediction. By using TOPICS with CDBM model, JT-60SA ITB plasmas with high 
and full CD condition have been predicted consistently with Ar seeding to reduce the heat load on divertor plates below 10 MW/m
. In the prediction, TOPICS is coupled with impurity transport code IMPACT to examine the Ar core accumulation for the influx to the core and the separatrix density evaluated by integrated divertor code SONIC. The Ar accumulation is found to be so mild that the performance can be recovered by additional heating. Due to the strong dependence of accumulation on the pedestal density gradient, the high separatrix density is important for low accumulation as well as low divertor heat load.
