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Observation and evaluation of plastic collapse for double-notch pipe

鈴木 良祐*; 松原 雅昭*; 坂本 賢治*; 鈴木 将人*; 白石 泰祐*; 柳原 星児*; 伊沢 悟*; 若井 隆純

Experimental Techniques, 40(1), p.253 - 260, 2016/09

 被引用回数:0 パーセンタイル:100(Engineering, Mechanical)



Advance in integrated modelling towards prediction and control of JT-60SA plasmas

林 伸彦; 本多 充; 白石 淳也; 宮田 良明; 若月 琢馬; 星野 一生; 藤間 光徳; 鈴木 隆博; 浦野 創; 清水 勝宏; et al.

Europhysics Conference Abstracts (Internet), 39E, p.P5.145_1 - P5.145_4, 2015/06

Towards prediction and control of JT-60SA plasmas, we are developing codes/models which can describe physics/engineering factors, and integrating them to one code TOPICS. Physics modelling: Coupling with MINERVA/RWMaC code showed that MHD equilibrium variation by centrifugal force largely affects RWM stability and the toroidal rotation shear stabilizes RWM. Coupling with OFMC code for NB torques, 3D MHD equilibrium code VMEC and drift-kinetic code FORTEC-3D for NTV torque, and toroidal momentum boundary model, predicted the core rotation of $$sim$$2% of Alfv$'e$n speed for a ITER hydrogen L-mode plasma. Coupling with core impurity transport code IMPACT showed the accumulation of Ar seeded to reduce the divertor heat load is so mild that plasma performance can be recovered by additional heating in JT-60SA steady-state (SS) scenario. Simulations coupled with MARG2D code showed that plasma current can be ramped-up to reach $$beta_N ge$$3 with MHD modes stabilized by ideal wall and with no additional flux consumption of central solenoid in JT-60SA. Engineering modelling: Coupling with integrated real-time controller showed that simultaneous control of $$beta_N$$ and $$V_{loop}$$ is possible at $$beta_N ge$$4 in JT-60SA SS scenarios. MHD equilibrium control simulator MECS demonstrated equilibrium control during heating phase and collapse induced events within power supply capability of PF coils in JT-60SA.


Current ramp-up scenario with reduced central solenoid magnetic flux consumption in JT-60SA

若月 琢馬; 鈴木 隆博; 林 伸彦; 白石 淳也; 井手 俊介; 高瀬 雄一*

Europhysics Conference Abstracts (Internet), 39E, p.P5.144_1 - P5.144_4, 2015/06

We have investigated reduction of the CS flux required in the plasma current ramp-up phase using non-inductive current drive in JT-60SA with an integrated modeling code suite (TOPICS). JT-60SA will be equipped with various types of neutral beams different in the beam trajectories and energies (85 keV and 500 keV). We have made a scenario in which the plasma current is ramped up from 0.6 MA to 2.1 MA in 150 s with no additional CS flux consumption by overdriving the plasma current ($$I_{rm NI} > I_{rm p}$$, $$I_{rm NI}$$ : non-inductively driven current and $$I_{rm p}$$ : plasma current) with neutral-beam-driven and bootstrap current. In order to achieve the current overdrive condition from 0.6 MA, the current drive by the lower energy neutral beam injection (85 keV) is effective. The higher energy neutral beam injection (500 keV) cannot be utilized in this early phase with a low plasma density due to a large shine through loss, while it can effectively be utilized in the later phase. We have also investigated ideal MHD instabilities using a linear ideal MHD stability analysis code (MARG2D). External kink modes can be stabilized in most of the time during the current ramp-up if there is a perfect conducting wall.


Simulation of plasma current ramp-up with reduced magnetic flux consumption in JT-60SA

若月 琢馬; 鈴木 隆博; 林 伸彦; 白石 淳也; 井手 俊介; 高瀬 雄一*

Plasma Physics and Controlled Fusion, 57(6), p.065005_1 - 065005_12, 2015/06

 被引用回数:7 パーセンタイル:53.27(Physics, Fluids & Plasmas)

Current ramp-up with reduced central solenoid (CS) flux consumption in JT-60SA has been investigated using an integrated modeling code suite (TOPICS) with a turbulent model (CDBM). The plasma current can be ramped-up from 0.6 MA to 2.1 MA with no additional CS flux consumption if the plasma current is overdriven by neutral-beam-driven and bootstrap current. The time duration required for the current ramp-up without CS flux consumption becomes as long as 150s. In order to achieve the current overdrive condition from 0.6 MA, the current drive by a lower energy neutral beam (85 keV) is effective. A higher energy neutral beam (500 keV) cannot be utilized in this early phase due to large shine through loss, while it can be effectively utilized in the later phase. Therefore, the main current driver should be switched from the lower energy neutral beam to the higher energy neutral beam during the current ramp-up phase. As a result of an intensive auxiliary heating needed to overdrive the plasma current, plasma beta becomes high. Ideal MHD stabilities of such high beta plasmas have been investigated using a linear ideal MHD stability analysis code (MARG2D). External kink modes can be stabilized in most of the time during the current ramp-up if there is a perfectly conducting wall at the location of the stabilizing plate and the vacuum vessel of JT-60SA and the plasma has a broader pressure profile.


In-situ dismantling of the liquid waste storage tank in the decommissioning program of the JRTF

三村 竜二; 村口 佳典; 中塩 信行; 根本 浩一; 白石 邦生

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 5 Pages, 2015/05



Experiences on research reactors decommissioning in the NSRI of the JAEA

立花 光夫; 岸本 克己; 白石 邦生

International Nuclear Safety Journal (Internet), 3(4), p.16 - 24, 2014/11



Extension of kinetic-magnetohydrodynamic model to include toroidal rotation shear effect and its application to stability analysis of resistive wall modes

白石 淳也; 宮戸 直亮; 松永 剛; 本多 充; 林 伸彦; 井手 俊介

Proceedings of 25th IAEA Fusion Energy Conference (FEC 2014) (CD-ROM), 8 Pages, 2014/10

トカマクプラズマにおいて発生する電磁流体力学(MHD: Magnetohydrodynamics)モードに対する、トロイダル回転シア効果及び運動論的効果を解明するため、運動論的MHDモデルの拡張を行った。回転の効果を含む案内中心ラグランジアンを用いて、運動論的MHDモデルの再定式化を行った。その結果、案内中心の運動がコリオリ力と遠心力の効果を受けて、MHDモードと粒子運動の共鳴によるエネルギー項が拡張されることを示した。また、平衡の分布関数に回転の効果を入れることでも拡張を行った。これらの効果は、従来の運動論的MHDモデルでは見落とされてきた。この拡張された運動論的MHDモデルをトカマク配位における抵抗性壁モード(RWM: Resistive Wall Mode)解析コードMINERVA/RWMaCに実装し、ベンチマークに成功した。また、当コードをJT-60Uを模擬した平衡に応用し、回転シア効果によって、RWMが粒子運動と共鳴してエネルギーが減衰することが明らかになった。


MHD instability excited by interplay between resistive wall mode and stable MHD modes in rotating tokamak plasmas

相羽 信行; 廣田 真*; 松山 顕之; 白石 淳也; Bierwage, A.

Proceedings of 25th IAEA Fusion Energy Conference (FEC 2014) (CD-ROM), 8 Pages, 2014/10



Effects of centrifugal modification of magnetohydrodynamic equilibrium on resistive wall mode stability

白石 淳也; 相羽 信行; 宮戸 直亮; 矢木 雅敏

Nuclear Fusion, 54(8), p.083008_1 - 083008_8, 2014/08

 被引用回数:8 パーセンタイル:51.48(Physics, Fluids & Plasmas)

磁気流体力学(MHD: Magnetohydrodynamics)平衡におけるトロイダル回転の遠心力効果を考慮することにより、MHD安定性における回転の効果を自己無撞着に取り入れた。抵抗性壁モード(RWM: Resistive Wall Mode)の安定性に対する回転の効果を解析するため、新しいコードを開発した。真空領域と抵抗性壁における電磁気学的な問題を解くモジュールRWMaCを開発し、回転プラズマにおける線形理想MHDダイナミクスを記述するFrieman-Rotenberg方程式を解くMINERVAコードに組み込んだ。MINERVA/RWMaCにより、トロイダル回転によるMHD平衡の変化が、RWMの成長率を減少させることを初めて示した。加えて、トロイダル回転が線形ダイナミクスにのみ影響を与える場合には安定化窓が存在しない場合でも、平衡の変化により安定化窓が現れることを示した。回転は、平衡の圧力、電流密度、質量密度を変化させ、回転の効果を含むポテンシャルエネルギーを変化させる。


On kinetic resistive wall mode theory with sheared rotation

白石 淳也; 宮戸 直亮; 松永 剛

Plasma and Fusion Research (Internet), 9, p.3403027_1 - 3403027_4, 2014/04

トカマクにおいてトロイダル回転シアが存在する場合の運動論的抵抗性壁モード(RWM: Resistive Wall Mode)の安定性を決定する分散関係を導出した。運動論的RWM理論では、分散関係はエネルギー汎関数により記述され、エネルギー汎関数は案内中心のラグランジアンによって特徴付けられる。しかし、従来の運動論的RWM理論では、回転が小さいとして、回転の効果を含まないラグランジアンを用いてきた。本研究では、回転シアがある場合にはラグランジアンは一般化されることに着目し、一般化されたラグランジアンを用いて、運動論的RWM理論による分散関係の構造について調べた。その結果、エネルギー汎関数は、従来の磁場曲率に起因する項に加えて、案内中心の遠心力加速による項が付け加わることが分かった。大アスペクト比近似のもと数値解析を行ったところ、新しいエネルギー汎関数は虚部を持つため、減衰効果を持つことが分かった。また、回転シアにより、RWMが安定化されることが明らかになった。これは、JT-60Uで観測された実験結果の傾向と一致している。


Order effect of repair processes to clustered DNA damage

白石 伊世; 鈴木 雅雄*; 鹿園 直哉; 藤井 健太郎; 横谷 明徳

Journal of Radiation Research, 55(Suppl.1), p.i92 - i93, 2014/03

In a living cell, cluster DNA damage is thought to be processed by several different pathways simultaneously or sequentially. Under this situation the cellular response to cluster DNA might depend on the order of repair processes because the configuration of the lesions will be modified by the reaction of initial repair protein, affecting the DNA-binding or excision activities of latter proteins. In the present study, we investigate whether initial enzymatic repair affects latter processes. Plasmid DNA exposed to C ion is treated with two base excision repair enzymes, Nth and Fpg, which convert pyrimidine and purine lesions to a SSB, respectively. Obtained results show that the amount of enzymatically induced SSB is very slightly less in DNA sample treated with Nth first and then Fpg than that of other treatments. These results indicate that the configuration-change of the cluster by the first enzymatic treatment does not significantly influence the activity of secondary enzyme.


The Possible interplanetary transfer of microbes; Assessing the viability of ${it Deinococcus}$ spp. under the ISS environmental conditions for performing exposure experiments of microbes in the Tanpopo mission

河口 優子*; Yang, Y.*; 川尻 成俊*; 白石 啓祐*; 高須 昌子*; 鳴海 一成*; 佐藤 勝也; 橋本 博文*; 中川 和道*; 谷川 能章*; et al.

Origins of Life and Evolution of Biospheres, 43(4-5), p.411 - 428, 2013/10

 被引用回数:23 パーセンタイル:24.44(Biology)

In the Tanpopo mission, we have proposed to carry out experiments on capture and space exposure of microbes at the Exposure Facility of the Japanese Experimental Module of the International Space Station (ISS). Microbial candidates for the exposure experiments in space include ${it Deinococcus}$ spp. We have examined the survivability of ${it Deinococcus}$ spp. under the environmental conditions in ISS in orbit. A One-year dose of heavy-ion beam irradiation did not affect the viability of ${it Deinococcus}$ spp. within the detection limit. Exposure of various thicknesses of deinococcal cell aggregates to UV radiation revealed that a few hundred micrometer thick aggregate of deinococcal cells would be able to withstand the solar UV radiation on ISS for 1 year. We concluded that aggregated deinococcal cells will survive the yearlong exposure experiments. We propose that microbial cells can aggregate as an ark for the interplanetary transfer of microbes, and we named it "massapanspermia".


会議報告; 第16回若手科学者によるプラズマ研究会

本多 充; 白石 淳也; 相羽 信行

プラズマ・核融合学会誌, 89(5), P. 330, 2013/05



Spin-pump-induced spin transport in $$p$$-type Si at room temperature

仕幸 英治*; 安藤 和也*; 久保 和樹*; 齊藤 英治; 新庄 輝也*; 白石 誠司*

Physical Review Letters, 110(12), p.127201_1 - 127201_5, 2013/03

 被引用回数:119 パーセンタイル:2.29(Physics, Multidisciplinary)



Optimization of JT-60SA plasma operational scenario with capabilities of installed actuators

井手 俊介; 相羽 信行; Bolzonella, T.*; Challis, C. D.*; 藤田 隆明; Giruzzi, G.*; Joffrin, E.*; 濱松 清隆; 林 伸彦; 本多 充; et al.

Proceedings of 24th IAEA Fusion Energy Conference (FEC 2012) (CD-ROM), 8 Pages, 2013/03

Assessment of capabilities in controlling key plasma parameters to access and sustain a high normalized pressure plasma in JT-60SA has been carried out using predictive simulations with emphasis on controllability with actuators, including not only heating and current drive but also fueling and pumping system. It is confirmed that the safety factor profile, which is believed to play an important role for confinement improvement, can be prepared appropriately at the plasma current ramp-up phase in a wide extent within capability of the installed ECRF system. At the flat-top of a high pressure and high bootstrap current plasma, it is also confirmed that the installed NB system can modify the safety factor profile and the confinement property within the planned capabilities. It is confirmed that impurity seeding in the SOL and the divertor region can maintain the heat flux within the divertor heat tolerance keeping the separatrix density level acceptable.


Stabilization of resistive wall modes by magnetohydrodynamic equilibrium change induced by plasma toroidal rotation

白石 淳也; 相羽 信行; 宮戸 直亮; 矢木 雅敏

Proceedings of 24th IAEA Fusion Energy Conference (FEC 2012) (CD-ROM), 8 Pages, 2013/03

磁気流体力学(MHD: Magnetohydrodynamics)平衡におけるトロイダル回転の遠心力効果を考慮することにより、MHD安定性における回転の効果を自己無撞着に取り入れた。抵抗性壁モード(RWM: Resistive Wall Mode)の安定性に対する回転の効果を解析するため、新しいコードを開発した。真空領域と抵抗性壁における電磁気学的な問題を解くモジュールRWMaCを開発し、回転プラズマにおける線形理想MHDダイナミクスを記述するFrieman-Rotenberg方程式を解くMINERVAコードに組み込んだ。MINERVA/RWMaCにより、トロイダル回転によるMHD平衡の変化が、RWMの成長率を減少させることを初めて示した。加えて、トロイダル回転が線形ダイナミクスにのみ影響を与える場合には安定化窓が存在しない場合でも、平衡の変化により安定化窓が現れることを示した。回転は、平衡の圧力,電流密度,質量密度を変化させ、回転の効果を含むポテンシャルエネルギーを変化させる。


Induction of DNA damage, including abasic sites, in plasmid DNA by carbon ion and X-ray irradiation

椎名 卓也; 渡辺 立子; 白石 伊世; 鈴木 雅雄*; 菅谷 雄基; 藤井 健太郎; 横谷 明徳

Radiation and Environmental Biophysics, 52(1), p.99 - 112, 2013/03

 被引用回数:13 パーセンタイル:40.21(Biology)

Plasmid DNA was irradiated with carbon ions or X-rays in solutions containing several concentrations of Tris (0.66-200 mM) to determine the yield of abasic (AP) sites and the effect of scavenging capacity. The yield of AP sites, detected as single strand breaks (SSB) after digestion with E. coli endonucrease IV (Nfo), was compared with that of SSB and base lesions. At higher concentrations of Tris, the yields of single or clustered AP sites were significantly lower than those of single or clustered base lesions. The dependence of the yield of AP sites on scavenging capacity was similar to that of prompt strand breaks. These results indicate that the reaction of water radiolysis products, presumably OH radicals, with the sugar-phosphate moieties in the DNA backbone induces both AP sites and SSB with similar efficiency.


Impact of plasma rotation on the linear physics of resistive wall modes in tokamaks

相羽 信行; 白石 淳也; 廣田 真

Plasma Physics and Controlled Fusion, 55(7), p.074002_1 - 074002_7, 2013/00

 被引用回数:5 パーセンタイル:71.64(Physics, Fluids & Plasmas)



Experimental study for the proposal of design measures against cover gas entrainment and vortex cavitation with 1/11th scale reactor upper sodium plenum model of Japan Sodium-cooled Fast Reactor

吉田 和弘*; 坂田 英之*; 佐郷 ひろみ*; 白石 直*; 大山 一弘*; 萩原 裕之*; 山野 秀将; 山本 智彦

Proceedings of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-8) (USB Flash Drive), 9 Pages, 2012/12




柳原 星児*; 松原 雅昭*; 鈴木 良祐*; 鈴木 将人*; 白石 太祐*; 坂本 賢治*; 若井 隆純

日本機械学会M&M2012材料力学カンファレンス講演論文集(CD-ROM), 2 Pages, 2012/09

The fracture assessment of independent multiple flaws is not developed in the piping for nuclear power in the Japan Society of Mechanical Engineers maintenance standard. In the maintenance standard, an enough examination is not performed about the influence that the load history of the axial tension due to inner pressure and the bending such as the earthquake affects on collapse strength of the piping. This study clarified that the effect of multiple flaws affected on the plastic collapse strength of the stainless steel piping that loaded axial tension and bending independently, and proposed the maximum load evaluation method. Conclusions are as follows: (1) Multiple flaws on piping can be evaluated by the plastic collapse theory of the single flaw, and the flaw can be simplified, and a conservative evaluation of piping be done. (2) The maximum stress can be calculated from the flaw size and mechanical properties of piping and piping size.

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