研究者詳細 - 星野　一生

論文 - 星野　一生

分割表示 113 件中 81 - 100 件目／全件表示 >>

Development of the Backflow Model for Simplified Impurity Exhaust in Monte-Carlo Calculation

K. Hoshino, K. Shimizu, H. Kawashima, T. Takizuka, T. Nakano, S. Ide

Contributions to Plasma Physics 54 404 - 408 2014年06月

研究論文（学術雑誌）, 共著, 査読有り

Access to Document (DOI)

Divertor study on DEMO reactor

Hoshino Kazuo, Asakura Nobuyuki, Shimizu Katsuhiro, Tokunaga Shinsuke, Takizuka Tomonori, Someya Youji, Nakamura Makoto, Utoh Hiroyasu, Sakamoto Yoshiteru, Tobita Kenji

Plasma and Fusion Research 9 3403070 2014年06月

研究論文（学術雑誌）, 共著, 査読有り, ISSN 1880-6821

Huge power handling in the SOL/divertor region is one of the crucial issues for a tokamak fusion reactor. Divertor design study of a DEMO reactor with fusion power of 3 GWand ITER size plasma has progressed using the integrated divertor code SONIC. Recently, to improve conversion of the solution for the DEMO divertor plasma simulation, SONIC code has been improved. The calculation time is significantly reduced by (i) the backflow model for the simplified impurity exhaust process and (ii) optimization on HELIOS at BA-IFERC. In the SONIC simulation, the partial detached divertor plasma was obtained by the Ar impurity seeding. Although the plasma heat load at the outer target was reduced by the partial detachment, the contribution of the impurity radiation and the surface recombination of the fuel ions to the target heat load became large. As a result, the peak of the total target heat load was estimated to be 16MW/m². In order to reduce the total heat load, control of the impurity radiation profile by kind of seeding impurity species and the divertor geometry has been studied. They can decrease the target heat load, but the peak heat load is still larger than the heat removal capability of the present divertor target concept. Further design study including change of the machine specifications is necessary.

Access to Document (DOI)

Systematic Study of Tungsten Impurity Transport in Representative Regimes of Divertor Plasma

Yamoto, S., Hoshino, K., Toma, M., Homma, Y., Hatayama, A., Bonnin, X., Coster, D., Schneider, R.

CONTRIBUTIONS TO PLASMA PHYSICS 54 （ 4-6 ） 421 - 425 2014年06月

研究論文（学術雑誌）, 共著, 査読有り, ISSN 0863-1042

Access to Document (DOI)

A simulation study of large power handling in the divertor for a Demo reactor

Asakura Nobuyuki, Shimizu Katsuhiro, Hoshino Kazuo, Tobita Kenji, Tokunaga Shinsuke, Takizuka Tomonori

Nuclear Fusion 53 （ 12 ） 123013 2013年12月

研究論文（学術雑誌）, 共著, 査読有り, ISSN 0029-5515

Power exhaust for a 3 GW class fusion reactor with an ITER-sized plasma was investigated by enhancing the radiation loss from seeding impurity. The impurity transport and plasma detachment were simulated under the Demo divertor condition using an integrated divertor code SONIC, in which the impurity Monte-Carlo code, IMPMC, can handle most kinetic effects on the impurity ions in the original formula. The simulation results of impurity species from low Z (neon) to high Z (krypton) and divertor length with a plasma exhausted power of 500 MW and radiation loss of 460 MW, and a fixed core-edge boundary of 7 × 10¹⁹ m^-3 were investigated at the first stage for the Demo divertor operation scenario and the geometry design. Results for the different seeding impurities showed that the total heat load, including the plasma transport and radiation , was reduced from 15-16 MW m^-2 (Ne and Ar) to 11 MW m^-2 for the higher Z (Kr), and extended over a wide area accompanied by increasing impurity recycling. The geometry effect of the long-leg divertor showed that full detachment was obtained, and the peak qtarget value was decreased to 12 MW m^-2, where neutral heat load became comparable to and due to smaller flux expansion. Fuel dilution was reduced but was still at a high level. These results showed that a divertor design with a long leg with higher Z seeding such as Ar and Kr is not fulfilled, but will be appropriate to obtain the divertor scenario for the Demo divertor. Finally, influences of χ and D enhancement were seen significantly in the divertor, i.e. the radiation and density profiles became wider, leading to full detachment. Both qtarget near the separatrix and Te at the outer flux surfaces were decreased to a level for the conventional technology design. On the other hand, the problem of fuel dilution became worse. Extrapolation of the plasma transport coefficients to ITER and Demo, where density and temperature will be higher than ITER and edge-localized modes are mitigated, is a key issue for the divertor design.

Access to Document (DOI)

Critical design factors for sector transport maintenance in DEMO

Utoh Hiroyasu, Someya Youji, Tobita Kenji, Asakura Nobuyuki, Hoshino Kazuo, Nakamura Makoto

Nuclear Fusion 53 （ 12 ） 123005 2013年12月

研究論文（学術雑誌）, 共著, 査読有り, ISSN 0029-5515

This paper mainly focuses on a sector transport maintenance scheme from the aspects of high plant availability. In this study, three different maintenance schemes are considered based on (1) the number of maintenance ports and (2) the insertion direction. The design study clarifies critical design factors and key engineering issues on the maintenance scheme: (1) how to support an enormous overturning force of the toroidal field coils in the large open port for sector transport and (2) define the transferring mechanism of sectors in the vacuum vessel. On reviewing these assessment factors, the sector transport using a limited number of horizontal maintenance ports is found to be a more realistic maintenance scheme. In addition, evaluating maintenance scenarios under high decay heat is proposed for the first time. The key design factors are the cool-down time in the reactor and the cooling method in the maintenance scheme to keep components under operational temperature. Based on one-dimensional heat conduction analysis, after one month cool-down time, each sector of SlimCS could be transported to the hot cell facility by gas cooling.

Access to Document (DOI)

Effects of Neutral Particles on the Stability of the Detachment Fronts in Divertor Plasmas

S. Togo, M. Nakamura, Y. Ogawa, K. Shimizu, T. Takizuka, K. Hoshino

Plasma Fusion Research 8 2403096 2013年08月

研究論文（学術雑誌）, 共著, 査読有り

Access to Document (DOI)

Comparison of kinetic and fluid models for tungsten impurity transport using IMPGYRO and SOLPS

Toma, M., Bonnin, X., Sawada, Y., Homma, Y., Hatayama, A., Hoshino, K., Coster, D., Schneider, R.

JOURNAL OF NUCLEAR MATERIALS 438 S620 - S624 2013年07月

研究論文（学術雑誌）, 共著, 査読有り, ISSN 0022-3115

Access to Document (DOI)

Investigation of advanced divertor magnetic configuration for DEMO tokamak reactor

N. Asakura, K. Shinya, K. Tobita, K. Hoshino, K. Shimizu, H. Utoh, Y. Someya, M. Nakamura, N. Ohno, M. Kobayashi, H. Tanaka

Fusion Science and Technology 63 70 - 75 2013年03月

研究論文（国際会議プロシーディングス）, 共著, 査読有り

Effects of radial losses of particle and energy on the stability of detachment front in a divertor plasma

Togo Satoshi, Nakamura Makoto, Ogawa Yuichi, Shimizu Katsuhiro, Takizuka Tomonori, Hoshino Kazuo

Plasma and Fusion Research 7 2401087 2012年12月

研究論文（学術雑誌）, 共著, 査読有り, ISSN 1880-6821

Operation under partially detached divertor (PDD) plasmas is a hopeful way in order to reduce the divertor heat load in the next generation tokamaks. The physical mechanism of PDD plasmas, however, has not fully been understood yet. We have studied them with a multi-layer one-dimensional divertor model. The PDD plasmas are successfully reproduced by introducing a neutral gas puffing model. Effect of the cross-field heat transport on the PDD plasmas is investigated. It is found that cross-field heat transport both in the SOL region and in the divertor region prevents detachment fronts from moving upstream in a detached flux tube.

Access to Document (DOI)

Simulation Study of L/H Transition with Self-Consistent Integrated Modelling of Core and SOL/Divertor Transport

Yagi, M., Shimizu, K., Takizuka, T., Honda, M., Hayashi, N., Hoshino, K., Fukuyama, A.

CONTRIBUTIONS TO PLASMA PHYSICS 52 （ 5-6 ） 372 - 378 2012年06月

研究論文（学術雑誌）, 共著, 査読有り, ISSN 0863-1042

Access to Document (DOI)

Simulation Study of an Extended Divertor Leg for Heat Control in the SlimCS DEMO Reactor

Hoshino, K., Shimizu, K., Asakura, N., Takizuka, T., Nakamura, M., Tobita, K.

CONTRIBUTIONS TO PLASMA PHYSICS 52 （ 5-6 ） 550 - 554 2012年06月

研究論文（学術雑誌）, 共著, 査読有り, ISSN 0863-1042

Access to Document (DOI)

Development of Coupled IMPGYRO-SOLPS Codes for Analyzing Tokamak Plasmas with Tungsten Impurities

Toma, M., Bonnin, X., Hoshino, K., Hatayama, A., Schneider, R., Coster, D.

CONTRIBUTIONS TO PLASMA PHYSICS 52 （ 5-6 ） 450 - 454 2012年06月

研究論文（学術雑誌）, 共著, 査読有り, ISSN 0863-1042

Access to Document (DOI)

Integrated modeling of whole Tokamak plasma

Hayashi Nobuhiko, Honda Mitsuru, Hoshino Kazuo, Hamamatsu Kiyotaka, Shimizu Katsuhiro, Takizuka Tomonori, Ozeki Takahisa, Fukuyama Atsushi

Plasma and Fusion Research 6 2403065 2011年12月

研究論文（学術雑誌）, 共著, 査読有り, ISSN 1880-6821

Development and integration of models for the whole tokamak plasma have progressed on the basis of experimental analyses and first principle simulations. Integrated models of core, edge-pedestal and scrape-offlayer (SOL)-divertor clarified complex and autonomous features of reactor relevant plasmas. The integrated core plasma model including an anomalous transport of alpha particles by Alfven eigenmodes is developed in the core transport code TOPICS-IB and indicates the degradation of fusion performance. The integrated rotation model is developed in the advanced transport code TASK/TX and clarifies the mechanism of alpha particle-driven toroidal flow. A transport model of high-Z impurities is developed and predicts large inward pinch in a plasma rotating in the direction counter to the plasma current. TOPICS-IB is extended to include the edge-pedestal model by integrating with the stability code, simple SOL-divertor and pellet models, and clarifies the mechanism of pellet triggered ELM. The integrated SOL-divertor code SONIC is further integrated with TOPICS-IB and enables to study and design operation scenarios compatible with both the high confinement in the core and the low heat load on divertor plates.