学術論文

当チームメンバーが執筆し掲載された雑誌と内容の一覧です

2022年

5th DEMO Programme Workshop

S. Kakudate, “DEMO Service Joining Technology” (invited)

Y. Sakamoto, S. Tokunaga, N. Hayashi, T. Wakatsuki, S. Ide, K. Tobita and the Joint Special Design Team for Fusion DEMO, “Operation scenario development and control issues on DEMO”

2021年

Power Exhaust Studies and Divertor Designs for Japanese and European DEMO Fusion Reactors

N. Asakura, K. Hoshino, S. Kakudate, F. Subba, C. Vorpahl, Y. Homma, H. Utoh, Y. Someya, Y. Sakamoto, R. Hiwatari, S. Suzuki, M. Siccinio, G. Federici, J.-H. You

Nuclear Fusion 61 (2021) 126057

Hydrogen permeation behavior through tungsten deposition layer

H. Ito, K. Katayama, D. Mori, Y. Hara and M. Oya

Fusion Eng. Design 162 (2021) 112083

Study on pulse shape dependence of tungsten mass erosion under disruption-like heat load

D. Motoi, K. Ibano, Y. Kikuchi, S. Saito, T. Okita, E. Hoashi, H. Lee, Y. Ueda

Fusion Eng. Design 165 (2021) 112209

The T-containment properties of a Zr-containing Li rod in a high-temperature gas-cooled reactor as a T production device for fusion reactors

H. Matsuura, T. Suganuma, Y. Koga, M. Naoi, K. Katayama, T. Otsuka, M. Goto, S. Nakagawa, S. Hamamoto, E. Ishitsuka, K. Tobita, S. Konishi, R. Hiwatari, Y. Someya, Y. Sakamoto

Fusion Eng. Design 169 (2021) 112441

Effect of temperature distribution on tritium permeation rate to cooling water in JA DEMO condition

K. Katayama, Y. Someya, T. Chikada, K. Tobita, H. Nakamura, Y. Hatano, R. Hiwatari, Y. Sakamoto, A. Ipponsugi, M. Oya

Fusion Eng. Design 169 (2021) 112576

A study on ohmic plasma initiation for JA DEMO

S. Sugiyama, K. Shinya, H. Utoh, N. Aiba, Y. Sakamoto

Fusion Eng. Design 172 (2021) 112779

Evaluation of hydrogen retention behavior in tungsten exposed to hydrogen plasma in QUEST

A. Koike, M. Nakata, S. Yamazaki, T. Wada, F. Sun, M. Zhao, N. Yoshida, K. Hanada, Y. Oya

Nuclear Materials and Energy 26 (2021) 100856

Simulation studies of the divertor detachment and critical power exhaust parameters for Japanese DEMO design

N. Asakura, K. Hoshino, Y. Homma, and Joint Special Design Team for Fusion Demo

Nuclear Materials and Energy 26 (2021) 100864

Observation of surface deformation of tungsten exposed to single pulsed high heat flux and magnetic field for divertor design

T. Okita, Y. Matsuda, S. Saito, E. Hoashi, K. Ibano, Y. Ueda

Fusion Eng. Design 171 (2021) 112547

Modeling of hydrogen permeation behavior through tungsten deposition layer growing on nickel substrate by hydrogen plasma sputtering

Y. Hara, K. Katayama and M. Oya

Fusion Eng. Design 172 (2021) 112851

Deuterium retention in tungsten irradiated by high-dose neutrons at high temperature

M. Oya, M. Shimada, C.N. Taylor, M.I. Kobayashi, Y. Nobuta, Y. Yamauchi, Y. Oya, Y. Ueda, Y. Hatano

Nuclear Materials and Energy 27 (2021) 100980

Overview of recent progress on steady state operation of all-metal plasma facing wall device QUEST

K. Hanada, N. Yoshida, M. Hasegawa, M. Oya, Y. Oya, I. Takagi, A. Hatayama, T. Shikama, H. Idei, Y. Nagashima, R. Ikezoe, T. Onchi, K. Kuroda, S. Kawasaki, A. Higashijima, T. Nagata, S. Shimabukuro, K. Nakamura, S. Murakami, Y. Takase, X. Gao, H. Liu, and J. Qian

Nuclear Materials and Energy 27 (2021) 101013

Effects of Helium Seeding on Deuterium Retention in Neutron-Irradiated Tungsten

Y.Nobuta, M.Shimada, C.N.Taylor, Y.Oya, Y.Hatano, Y.Wu and M.Dubey

Fusion Sci. Tech. 77 (2021) 76-79

Thermal treatment of W large-scale fiberform nanostructures

S.Kajita, T.Okuyama, H.Tanaka, T. Kuwabara, N.Ohno and N.Yoshida

Physica Scripta 96 (2021) 094004

Pulse Shape Dependence of Vapor Shielding Efficiencies During Transient Heat Loads

K. Ibano, Y. Ueda, T. Takizuka

Plasma and Fusion Research 16 (2021) 1405092

Simulation of Experimental Deuterium Retention in Tungsten under Periodic Deuterium Plasma Irradiation

M. Oya, Y. Hara, K. Katayama, K. Ohya

Plasma and Fusion Research 16 (2021) 2405057

Tungsten Large-Scale Fiberform Nanostructures Retained under High Temperature Conditions

T. Okuyama, S.Kajita, N.Yoshida, H.Tanaka, T.Kuwabara, N.Ohno

Plasma and Fusion Research 16 (2021) 1206001

2020年

Analysis of peak heat load on the blanket module for JA DEMO

Y. Miyoshi, R. Hiwatari, Y. Someya, S. Tokunaga, Y. Homma, N. Asakura, Y. Sakamoto, K. Tobita, The Joint Special Design Team for Fusion DEMO

Fusion Eng. Design 151 (2020) 111394

Effect of collisionality dependence of thermal force on impurity transport under lower collisional condition in DEMO scrape-off layer plasma

Y. Homma, K. Hoshino, S. Yamoto, S. Tokunaga, N. Asakura, Y. Sakamoto and Joint Special Design Team for Fusion DEMO

Nucl. Fusion 60 (2020) 046031

Effect of dragged magnetic field lines into RAFM steel blanket modules on first wall heat load

Y. Miyoshi, R. Hiwatari, Y. Someya, N. Asakura, S. Tokunaga, Y. Homma Y. Sakamoto, The Joint Special Design Team for Fusion DEMO

Fusion Eng. Design 156 (2020) 111568

Estimation of Magnetic Error Field with Alleviating Fabrication Tolerance of Large Superconducting Magnets on JA DEMO reactor

H. Utoh, G. Matsunaga, H. Togashi, R. Hiwatari, Y. Sakamoto, K. Tobita, and Joint Special Design Team for Fusion DEMO

Fusion Eng. Design 161 (2020) 111900

Deuterium recombination coefficient on tungsten surface determined by plasma driven permeation

M. Zhao, S. Yamazaki, T. Wada, A. Koike, F. Sun, N. Ashikawa, Y. Someya, T. Mieno, Y. Oya

Fusion Eng. Design 160 (2020) 111853

Empirical Formulas for Estimating Self and Mutual Inductances of Toroidal Field Coils and Structures

Y. Itoh, H. Utoh, Y. Sakamoto, R. Hiwatari and Joint Special Design Team for Fusion DEMO

Plasma and Fusion Research 15 (2020) 1405078

Dependence of Operation Density on the Density Profile Shape in DEMO Plasmas with Ar Injection for Divertor Heat Load Reduction

R. Sakai, T. Fujita, A. Okamoto

Plasma and Fusion Research 15 (2020) 1303031

High-Speed Analysis of Heating and Current Drive with Neutral Beam Injection in Tokamak Plasma

R. Funabashi, T. Fujita, A. Okamoto

Plasma and Fusion Research 15 (2020) 2401071

Atomic and Molecular Processes in Plasma Decomposition Method of Hydrocarbon Gas

M. Oya, R. Ikeda and K. Katayama

Plasma and Fusion Research 15 (2020) 2405032

Measurement of Dynamic Retention with Fast Ejecting System of Targeted Sample (FESTA)

Q. Yue, K. Hanada, M. Oya, S. Matsuo, S. Kojima, H. Idei, T. Onchi, K. Kuroda, N. Yoshida, R. Ikezoe, Y. Liu, M. Hasegawa, S. Shimabukuro, A. Higashijima, T. Nagata and S. Kawasaki

Plasma and Fusion Research 15 (2020) 2402013

Helium-W co-deposition layer: TEM observation and D retention

S.Kajita, K. Asai, N. Ohno, H. Tanaka, N. Yoshida, D. Nagata and M. Yajima

Journal of Nuclear Materials 540 (2020) 152350

Tungsten fuzz: Deposition effects and influence to fusion devices

S. Kajita, N. Yoshida and N. Ohno

Nuclear Materials and Energy 25 (2020) 100828

Spatiotemporal dynamics of cross-field ejection events in recombining detached plasma

H. Tanaka, S. Kajita, H. Natsume, I. Saeki and N. Ohno

Plasma Phys. Control. Fusion 62 (2020) 075011

D retention and depth profile behavior for single crystal tungsten with high temperature neutron irradiation

Y.Oya, F.Sun, Y.Yamauchi, Y.Nobuta, M.Shimada, C.N.Taylor, W.R.Wampler, M.Nakata, L.M.Garrison, Y.Hatano

Journal of Nuclear Materials 539 (2020) 152323

Potential contribution of fusion power generation to low-carbon development under the Paris Agreement and associated uncertainties

K. Gi , F. Sano , K. Akimoto , R. Hiwatari , K. Tobita

Energy Strategy Reviews 27 (2020) 100432

2019年

Assessment on tokamak fusion power plant to contribute to global climate stabilization in the framework of Paris Agreement

R. Hiwatari, T. Goto and Joint Special Design Team for Fusion DEMO

Plasma and Fusion Research 14 (2019) 1305047

Progress on reliability of remote maintenance concept for JA DEMO

H. Utoh, S. Kakudate, R. Hiwatari, Y. Someya, Y. Sakamoto, N.Asakura, S. Tokunaga, K. Tobita, Joint Special Design Team for Fusion Demo

Fusion Eng. Design 146 (2019) 1583-1586

Development of a water-cooled blanket concept with pressure tightness against in-box LOCA for Japan’s DEMO

Y. Someya, H. Kudo, K. Tobita, R. Hiwatari, Y. Sakamoto and Joint Special Design Team for Fusion DEMO

Fusion Eng. Design 146 (2019) 894-897

Development of plant concept related to tritium handling in the water-cooling system for JA DEMO

R. Hiwatari, K. Katayama, M. Nakamura, Y. Miyoshi, A. Aoki, Y. Someya, Y. Sakamoto, K. Tobita and the Joint Special Design Team for Fusion DEMO

Fusion Eng. Design 143 (2019) 259-266

Surface oxidation effect on deuterium permeation in reduced activation ferritic steel F82H for DEMO application

T. Chikada, K. Kimura, J. Mochizuki, S. Horikoshi, M. Matsunaga,H. Fujita, K. Okitsu, T. Tanaka, Y. Hishinuma, Y. Sakamoto, Y. Someya, H. Nakamura

Fusion Eng. Design 146 (2019) 450-454

"Deuterium permeation behavior through reduced activation ferritic steel F82H under DEMO reactor blanket condition"

K. Kimura, J. Mochizuki, S. Horikoshi, M. Matsunaga, H. Fujita, K. Okitsu, Y. Sakamoto, Y. Someya, H. Nakamura and T. Chikada

Fusion Eng. Design 146 (2019) 1564-1568

Japan's efforts to develop the concept of JA DEMO during the past decade

K. Tobita, R. Hiwatari, Y. Sakamoto, Y. Someya, N. Asakura, H. Utoh, Y. Miyoshi, S. Tokunaga, Y. Homma, N. Nakajima and the Joint Special Design Team for Fusion DEMO

Fusion Sci. Tech. 75 (2019) 372-383

Conceptual design of Japan’s fusion DEMO reactor, JA DEMO, and superconducting coil issues

K. Tobita, H. Utoh, R. Hiwatari, Y. Miyoshi, S. Tokunaga, Y. Sakamoto, Y. Someya, N. Asakura, Y. Homma, N. Nakajima and the Joint Special Design Team for Fusion DEMO

Journal of Physics:Conference Series 1293 (2019) 012078

Li-rod structure in high-temperature gas-cooled reactor as a tritium production device for fusion reactors

H. Matsuura, R. Okamoto, Y. Koga, T. Suganuma, K. Katayama, T. Otsuka, M. Goto, S. Nakagawa, E. Ishitsuka, K. Tobita

Fusion Eng. Design 146 (2019) 1077-1081

A Fast Discharge Scheme of Toroidal Field Coils for Fusion Demo Reactors

Y. Itoh, H. Utoh, Y. Sakamoto, R. Hiwatari and Joint Special Design Team for Fusion DEMO

Plasma and Fusion Research 14 (2019) 1405167

An Analysis of Japan’s Long-Term Energy Systems Reflecting Fusion Energy Development Roadmap by Using a Global Energy Systems Model

K. Gi, F. Sano, K. Akimoto, R. Hiwatari, K. Tobita

Journal of Japan Society of Energy and Resources, 40 (2019) 170-179

2018年

“Evaluation of tritium leakage rate into seawater in fusion DEMO cooling water system”

Y. Miyoshi, A. Aoki, R. Hiwatari, Y. Sakamoto, K. Tobita, the Joint Special Design Team for Fusion DEMO

Fusion Eng. Design 136 Part B 1577 (2018)

“Studies of the Plasma Vertical Instability and its Stabilized Concepts in JA and EU Broader Approach, DEMO Design Activity”

H. Utoh, S. Tokunaga, N. Asakura, Y. Sakamoto, Y. Someya, R. Hiwatari, K. Tobita, G. Federici, R. Wenninger, F. Maviglia, R. Albanese, R. Ambrosino, M. Mattei, F. Villone

DEMO Design Activity”, Fusion Eng. Design 136 (2018) 874-877

“Fusion DEMO reactor design based on nuclear analysis”

Y. Someya, K. Tobita, R. Hiwatari, Y. Sakamoto, the Joint Special Design Team for Fusion DEMO

Fusion Eng. Design 136 (2018) 1306-1312

“Modeling of chemical reactions of beryllium/beryllide pebbles with steam for hydrogen safety design of water-cooled DEMO”

M. Nakamura, J.-H. Kim, M. Nakamichi, Y. Someya, K. Tobita, Y. Sakamoto, R. Hiwatari, the Joint Special Design Team for Fusion DEMO

Fusion Eng. Design 136 (2018) 1484-1488

“An extended kinetic model for the thermal force on impurity particles in weakly collisional plasmas”

Yuki HOMMA, K. Hoshino, S. Tokunaga, S. Yamoto, A. Hatayama,N. Asakura, Y. Sakamoto, K. Tobita and Joint Special Design Team for Fusio DEMO

Contributions to Plasma Physics 58 (2018) p. 629-637

“Cooling water system design of Japan's DEMO for fusion power production”

Yuya MIYOSHI, Akira AOKI, Ryoji HIWATARI, Youji SOMEYA, Yoshiteru SAKAMOTO, Kenji TOBITA, The Joint Special Design Team for Fusion DEMO

Fusion Eng. Design 126 (2018) 110-115

2017年

“Design Strategy and Recent Design Activity on Japan’s DEMO”

Kenji Tobita, Nobuyuki Asakura, Ryoji Hiwatari, Youji Someya, Hiroyasu Utoh, Kazunari Katayama, Arata Nishimura, Yoshiteru Sakamoto, Yuki Homma, Hironobu Kudo, Yuya Miyoshi, Makoto Nakamura, Shunsuke Tokunaga, Akira Aoki & the Joint Special Design Team for Fusion DEMO

Fusion Sci. Tech. 72, 537-545 (2017)

“Power exhaust and divertor concept design for 1.5 GW class fusion power DEMO reactor”

N. Asakura, K. Hoshino, H. Utoh, Y. Someya, S. Tokunaga, S. Suzuki, K. Ezato, Y. Seki, H. Kudou, K. Shimizu, Y. Sakamoto, R. Hiwatari, K. Tobita, N. Ohno, Y. Ueda and Joint Special Team for Demo Design

Nuclear Fusion, 57, 126050 (2017)

“Numerical analysis of tungsten erosion and deposition processes under a DEMO divertor plasma”

Yuki Homma, Kazuo Hoshino, Shohei Yamoto, Nobuyuki Asakura, Shinsuke Tokunaga, Akiyoshi Hatayama, Yoshiteru Sakamoto, Ryoji Hiwatari, Kenji Tobit

Nuclear Materials and Energy, 12 (2017) 323-328

“Radioactive Waste Studies in the Frame of the IEA Cooperative Program on the Environmental, Safety, and Economic Aspects of Fusion Power”

M. Zucchetti, Z. Chang, L. El-Guebaly, Jung-Hoon Han, B. Kolbasov, V. Khripunov, M. Riva, Y. Someya, R. Testoni & K. Tobita

Fusion Sci. Tech. 72, 609-615 (2017)

“Conceptual design study of pellet fueling system for DEMO”

S. Tokunaga, A. Matsuyama, Y. Someya, H. Utoh, Y. Sakamoto, N. Asakura, K. Tobita and Joint Special Design Team for Fusion DEMO

Fusion Eng. Design 123 620-623 (2017)

“New model of plasma heat load on the first wall”

Y. Miyoshi, N. Asakura, K. Hoshino, H. Takase, R. Hiwatari, Y. Someya, Y. Sakamoto, K. Tobita, Joint Special Design Team for Fusion DEMO

Fusion Eng. Design 124 267-270 (2017)

“Estimation of tritium permeation rate to cooling water in fusion DEMO condition”

K. Katayama, Y. Someya, K. Tobita, H. Nakamura, H. Tanigawa, M. Nakamura, N. Asakura, K. Hoshino, T. Chikada, Y. Hatano and S. Fukada

Fusion Science and Technology 71-3, 261-267 (2017)

“Technological assessment between vertical and horizontal remote maintenance schemes for DEMO reactor”

H. Utoh, R. Hiwatari, K. Tobita, Y. Someya, Y. Sakamoto, N. Asakura, S. Tokunaga, A. Aoki, and Joint Special Design Team for Fusion DEMO

Fusion Eng. Design 124 (2017) 596-599

“Shutdown dose rate assessment during replacement of in-vessel components for a fusion DEMO reactor”

Y. Someya, H. Utoh, R. Hiwatari, H. Tanigawa, K. Tobita and Joint Special Desing Team for Fusion DEMO

Fusion Eng. Design 124 615-618 (2017)

“Physics design study of the divertor power handling in 8m class DEMO reactor”

K. Hoshino, N. Asakura, S. Tokunaga, Y. Homma, K. Shimizu, Y. Sakamoto, K. Tobita and Joint Special Design Team for Fusion DEMO

Fusion Eng. Design 124, 352-355 (2017)

“Reduction of poloidal magnetic flux consumption during plasma current ramp-up in DEMO relevant plasma regimes”

T. Wakatsuki, T. Suzuki, N. Hayashi, J. Shiraishi, Y. Sakamoto, S. Ide, H. Kubo and Y. Kamada

Nuclear Fusion 57 (2017) 016015

“Progress of divertor study on DEMO design”

T. Wakatsuki, T. Suzuki, N. Hayashi, J. Shiraishi, Y. Sakamoto, S. Ide, H. Kubo and Y. Kamada

Nuclear Fusion 57 (2017) 016015

2016年

“Thermohydraulic Analysis of Accident Scenarios of a Fusion DEMO Reactor Based on Water-Cooled Ceramic Breeder Blanket: Analysis of LOCAs and LOVA”

M. Nakamura, K. Watanabe, K. Tobita, Y. Someya, H. Tanigawa, H. Utoh, Y. Sakamoto, T. Kunugi, T. Yokomine, W. Gulden

IEEE Trans. Plasma Sci., 44 (2016) 1689-1699

“Safety research on fusion DEMO in Japan: Toward development of safety strategy of a water-cooled DEMO”

M. Nakamura, K. Tobita, Y. Someya, H. Utoh, Y. Sakamoto, W. Gulden

Fusion Eng. Design, 109-111 (2016) 1417-1421

“Influence of hydrogen addition to a sweep gas on tritium behavior in a blanket model containing Li2TiO3 pebbles”

K. Katayama, Y. Someya, K. Tobita, S. Fukada, Y. Hatano and T.Chikada

Fusion Eng. Design, 113 (2016) 221-226

“Japanese endeavors to establish technological bases for DEMO”

Hiroshi Yamada, Ryuta Kasada, Akira Ozaki, Ryuichi Sakamoto, Yoshiteru Sakamoto, Hidenobu Takenaga, Teruya Tanaka, Hisashi Tanigawa, Kunihiko Okano, Kenji Tobita, Osamu Kaneko, Kenkichi Ushigusa

Fusion Engineering and Design, 109-111 (2016) 1318-1325

“STUDIES OF RADIOACTIVE MATERIAL MANАGEMENT IN THE FRAME OF THE IEA COOPERATIVE PROGRAM ON THE ENVIRONMENTAL, SAFETY AND ECONOMIC ASPECTS OF FUSION POWER”

M. Zucchetti, B. Kolbasov, M. Riva, Y. Someya, R. Testoni, K. Tobita, J-H. Han, V. Khripunov, Z. Chang, L. El-Guebaly

PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY, Vol. 39-4 (in Russian)

“Safety Studies of Plasma-Wall Events with AINA code for Japanese DEMO”

J.C. Rivas, M. Nakamura, Y. Someya, H. Takase, K.Tobita, J. Dies, A.de Blas, M. Fabbri, A. Riego

Fusion Eng. Design, 109-111 (2016) 1653-1657

“Analysis of Plasma Position Control for DEMO Reactor”

H. Takase, H. Utoh, Y. Sakamoto, K. Mori, T. Kudoa, K. Tobita

Fusion Eng. Design, 109-111 (2016) 1386-1391

“Conceptual design of temporary storage area in hot cell for fusion DEMO reactor”

M. Kondo, Y. Someya, M. Tsuji, S. Yanagihara, H. Utoh, T. Kato, K. Tobita, S. Matsuda

Journal of Plasma and Fusion Research, 11, 2405077 (2016)

“Identification of safety gaps for fusion demonstration reactors”

Y. Wu, Z. Chen, L. Hu, M. Jin, Y. Li, J. Jiang, J. Yu, C. Alejaldre, E. Stevens, K. Kim, D. Maisonnier, A. Kalashnikov, K. Tobita, D. Jackson and D. Perrault

Nature Energy, 1 (2016) 154