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Journal Articles

Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors, 1; Project overview and progress until 2020

Yamano, Hidemasa; Takai, Toshihide; Emura, Yuki; Fukuyama, Hiroyuki*; Higashi, Hideo*; Nishi, Tsuyoshi*; Ota, Hiromichi*; Morita, Koji*; Nakamura, Kinya*; Fukai, Hirofumi*; et al.

Proceedings of 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-13) (Internet), 12 Pages, 2022/09

This paper describes the project overview and progress of experimental and analytical studies conducted until 2020. Specific results in this paper are the measurement of the eutectic reaction rates and the validation of physical model describing the eutectic reaction in the analysis code through the numerical analysis of the B$$_{4}$$C-SS eutectic reaction rate experiments in which a B$$_{4}$$C pellet was placed in a SS crucible.

Journal Articles

Porous metal-organic frameworks containing reversible disulfide linkages as cathode materials for lithium-ion batteries

Shimizu, Takeshi*; Wang, H.*; Matsumura, Daiju; Mitsuhara, Kei*; Ota, Toshiaki*; Yoshikawa, Hirofumi*

ChemSusChem, 13(9), p.2256 - 2263, 2020/05

 Times Cited Count:24 Percentile:77.17(Chemistry, Multidisciplinary)

Journal Articles

Repeatability and reproducibility of measurements of low dissolved radiocesium concentrations in freshwater using different pre-concentration methods

Kurihara, Momo*; Yasutaka, Tetsuo*; Aono, Tatsuo*; Ashikawa, Nobuo*; Ebina, Hiroyuki*; Iijima, Takeshi*; Ishimaru, Kei*; Kanai, Ramon*; Karube, Jinichi*; Konnai, Yae*; et al.

Journal of Radioanalytical and Nuclear Chemistry, 322(2), p.477 - 485, 2019/11

 Times Cited Count:2 Percentile:21.58(Chemistry, Analytical)

We assessed the repeatability and reproducibility of methods for determining low dissolved radiocesium concentrations in freshwater in Fukushima. Twenty-one laboratories pre-concentrated three of 10 L samples by five different pre-concentration methods (prussian-blue-impregnated filter cartridges, coprecipitation with ammonium phosphomolybdate, evaporation, solid-phase extraction disks, and ion-exchange resin columns), and activity of radiocesium was measured. The z-scores for all of the $$^{137}$$Cs results were within $$pm$$2, indicating that the methods were accurate. The relative standard deviations (RSDs) indicating the variability in the results from different laboratories were larger than the RSDs indicating the variability in the results from each separate laboratory.

Journal Articles

Development of new corrosion test equipment simulating sulfuric acid decomposition gas environment in a thermochemical hydrogen production process

Hirota, Noriaki; Kasahara, Seiji; Iwatsuki, Jin; Imai, Yoshiyuki; Ohashi, Hirofumi; Yan, X.; Tachibana, Yukio

Zairyo To Kankyo, 68(6), p.137 - 142, 2019/06

New corrosion test equipment for high temperature gas of decomposed sulfuric acid was manufactured in order to ascertain flow rate of sulfuric acid in the piping, occurrence of sulfuric acid decomposition reaction in the equipment, and temperature distribution inside the furnace tube. The flow rate of the sulfuric acid solution was constantly measured using an ultrasonic flowmeter. The SO$$_{3}$$ concentration at the inlet of the test equipment was almost the same as that at the inlet of the sulfuric acid decomposer in the hydrogen production plant assuming a high-temperature gas cooled reactor hydrogen-power cogeneration system (GTHTR300C). On the other hand, during a test, leakage of sulfuric acid occurred from the fitting part at the outlet side. Hence the temperature distribution of the fitting part at the outlet side was investigated using fluid analysis. As a result, it was found that the temperature at the fitting was low enough to use fluorine joint grease when the distance was 0.05 m or more away from the outlet side pipe. An improved furnace tube was manufactured and the temperature was measured again at fitting part of the outlet side. The temperature was lower that the temperature limit of the joint grease and almost the same as the temperature distribution in the fluid analysis, and leakage of sulfuric acid has not occurred to date.

JAEA Reports

Excellent feature of Japanese HTGR technologies

Nishihara, Tetsuo; Yan, X.; Tachibana, Yukio; Shibata, Taiju; Ohashi, Hirofumi; Kubo, Shinji; Inaba, Yoshitomo; Nakagawa, Shigeaki; Goto, Minoru; Ueta, Shohei; et al.

JAEA-Technology 2018-004, 182 Pages, 2018/07

JAEA-Technology-2018-004.pdf:18.14MB

Research and development on High Temperature Gas-cooled Reactor (HTGR) in Japan started since late 1960s. Japan Atomic Energy Agency (JAEA) in cooperation with Japanese industries has researched and developed system design, fuel, graphite, metallic material, reactor engineering, high temperature components, high temperature irradiation and post irradiation test of fuel and graphite, high temperature heat application and so on. Construction of the first Japanese HTGR, High Temperature engineering Test Reactor (HTTR), started in 1990. HTTR achieved first criticality in 1998. After that, various test operations have been carried out to establish the Japanese HTGR technologies and to verify the inherent safety features of HTGR. This report presents several system design of HTGR, the world-highest-level Japanese HTGR technologies, JAEA's knowledge obtained from construction, operation and management of HTTR and heat application technologies for HTGR.

Journal Articles

Rechargeable batteries based on stable redox reactions of disulfide included in a metal-organic framework as ligands

Shimizu, Takeshi*; Wang, H.*; Tanifuji, Naoki*; Matsumura, Daiju; Yoshimura, Masashi*; Nakanishi, Koji*; Ota, Toshiaki*; Yoshikawa, Hirofumi*

Chemistry Letters, 47(5), p.678 - 681, 2018/05

 Times Cited Count:9 Percentile:33.87(Chemistry, Multidisciplinary)

Journal Articles

Design of pencil beam formation system for high-accuracy carbon-ion microsurgery

Arakawa, Kazuo; Oikawa, Masakazu*; Shimada, Hirofumi*; Kamiya, Tomihiro; Nakano, Takashi*; Yusa, Ken*; Kato, Hiroyuki*; Sato, Takahiro; Agematsu, Takashi; Kashiwagi, Hirotsugu; et al.

Proceedings of 4th Annual Meeting of Particle Accelerator Society of Japan and 32nd Linear Accelerator Meeting in Japan (CD-ROM), p.279 - 281, 2007/00

no abstracts in English

Journal Articles

A Project of the K900 JAERI superconducting AVF cyclotron at JAERI

Fukuda, Mitsuhiro; Okumura, Susumu; Ishii, Yasuyuki; Saito, Yuichi; Miyawaki, Nobumasa; Mizuhashi, Kiyoshi; Agematsu, Takashi; Kurashima, Satoshi; Chiba, Atsuya; Sakai, Takuro; et al.

Dai-14-Kai Kasokuki Kagaku Kenkyu Happyokai Hokokushu, p.302 - 304, 2003/00

no abstracts in English

JAEA Reports

User's guide of parallel program development environment (PPDE), The 2nd edition

Ueno, Koichi*; Ota, Hirofumi*; Takemiya, Hiroshi*; Imamura, Toshiyuki; Koide, Hiroshi; Matsuda, Katsuyuki*; Higuchi, Kenji; Hirayama, Toshio

JAERI-Data/Code 2000-023, p.287 - 0, 2000/03

JAERI-Data-Code-2000-023.pdf:34.96MB

no abstracts in English

JAEA Reports

User's guide of parallel program development environment (PPDE)

Ueno, Koichi*; Ota, Hirofumi*; Takemiya, Hiroshi*; Imamura, Toshiyuki; Koide, Hiroshi; Matsuda, Katsuyuki*; Higuchi, Kenji; Hirayama, Toshio

JAERI-Data/Code 2000-012, p.125 - 0, 2000/03

JAERI-Data-Code-2000-012.pdf:19.49MB

no abstracts in English

Journal Articles

Improvement of tritium accountancy technology for the ITER fuel cycle safety enchancement

Ohira, Shigeru; Hayashi, Takumi; Nakamura, Hirofumi; Kobayashi, Kazuhiro; Tadokoro, Takahiro*; Nakamura, H.*; Ito, Takeshi*; Yamanishi, Toshihiko; Kawamura, Yoshinori; Iwai, Yasunori; et al.

Nuclear Fusion, 40(3Y), p.519 - 525, 2000/03

 Times Cited Count:24 Percentile:59.01(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Development of a tritium fuel processing systems using an electrolytic reactor for ITER

Yamanishi, Toshihiko; Kawamura, Yoshinori; Iwai, Yasunori; Arita, Tadaaki*; Maruyama, T.*; Kakuta, Toshiya*; Konishi, Satoshi; Enoeda, Mikio; Ohira, Shigeru; Hayashi, Takumi; et al.

Nuclear Fusion, 40(3Y), p.515 - 518, 2000/03

 Times Cited Count:6 Percentile:21.01(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Distributed parallel scientific computing environment; SSP

Takemiya, Hiroshi; Ota, Hirofumi; Imamura, Toshiyuki; Koide, Hiroshi; Matsuda, Katsuyuki; Higuchi, Kenji; Hirayama, Toshio; Kasahara, Hironori*

Keisan Kogaku Koenkai Rombunshu, 4(1), p.333 - 336, 1999/05

no abstracts in English

Journal Articles

Demonstration of the integrated fusion fuel loop at the tritium process laboratory of the Japan Atomic Energy Research Institute

Yamanishi, Toshihiko; Konishi, Satoshi; Hayashi, Takumi; Kawamura, Yoshinori; Iwai, Yasunori; Maruyama, T.*; Kakuta, Toshiya*; Ohira, Shigeru; Nakamura, Hirofumi; Kobayashi, Kazuhiro; et al.

Fusion Technology, 34(3), p.536 - 540, 1998/11

no abstracts in English

Journal Articles

Improvement of tritium accountancy technology for the ITER fuel cycle safety enhancement

Ohira, Shigeru; Hayashi, Takumi; Nakamura, Hirofumi; Kobayashi, Kazuhiro; Tadokoro, Takahiro*; Nakamura, H.*; Ito, Takeshi*; Yamanishi, Toshihiko; Kawamura, Yoshinori; Iwai, Yasunori; et al.

Fusion Energy 1998, 3, p.1069 - 1072, 1998/10

no abstracts in English

Oral presentation

Design of the submillimeter-pencil beam transport system for carbon ion microsurgery therapy

Kashiwagi, Hirotsugu; Oikawa, Masakazu*; Shimada, Hirofumi*; Yuri, Yosuke; Agematsu, Takashi; Ishii, Yasuyuki; Saito, Yuichi; Sakai, Takuro; Okumura, Susumu; Kurashima, Satoshi; et al.

no journal, , 

The areas of age-related macular degeneration, tumor in brain pituitary and vascular lesions such as AVM (Arterio Venous Malformation) to be treated are 1$$times$$1 mm, 30$$times$$30 mm and 3$$times$$3 mm respectively. To treat these by heavy ion beam instead of surgical operation, not only the spatial resolution of the beam should be 100 micrometer to 1 mm, but also the formation of it be pencil-shaped, so that the diameter of beam hardly depends on the depth of it in the target. The pencil beam transport system was studied and designed for carbon microsurgery therapy, as a part of the 21st century COE program. In this study, one of the vertical beam lines of a heavy ion therapy facility to be constructed in Gunma University was a model for beam optics calculations. The parameters of the magnetic components such as bending magnets and quadrupole ones, were optimized to obtain a sub-millimeter beam on the target. The range shifter is inserted in the beam line to form spread out bragg peak. Effect of inserting range shifters were also estimated, especially for growth of beam emittance by scattering in the further calculation. The total layout of this system and the beam optics simulations are explained in detail in the poster session.

Oral presentation

Micro-ion-beam applications to life science

Fukuda, Mitsuhiro; Arakawa, Kazuo; Sato, Takahiro; Okumura, Susumu; Saito, Yuichi; Kashiwagi, Hirotsugu; Miyawaki, Nobumasa; Yuri, Yosuke; Ishii, Yasuyuki; Kobayashi, Yasuhiko; et al.

no journal, , 

no abstracts in English

Oral presentation

High-precision carbon-ion microsurgery system for the least invasive treatments of various tumors

Arakawa, Kazuo; Fukuda, Mitsuhiro*; Shimada, Hirofumi*; Sakai, Takuro; Sato, Takahiro; Oikawa, Masakazu*; Agematsu, Takashi; Kashiwagi, Hirotsugu; Okumura, Susumu; Kurashima, Satoshi; et al.

no journal, , 

no abstracts in English

Oral presentation

Conceptual design of small-sized high temperature gas-cooled reactor system for electricity generation and district heating

Kasuga, Shoji*; Kubota, Kenichi*; Okamoto, Futoshi*; Maekawa, Isamu*; Furihata, Noboru*; Saito, Masanao*; Kido, Yuji*; Ohashi, Hirofumi; Tachibana, Yukio; Kunitomi, Kazuhiko

no journal, , 

Conceptual design of a small-sized HTGR for electricity generation and district heating has been conducted by JAEA with support of Japanese vendors: Toshiba Corporation, Fuji Electric, Kawasaki Heavy Industries, Nuclear Fuel Industries, Shimizu Corporation, and Marubeni Utility Services. System design as well as nuclear design of the first core of HTR50S using the same CFPs as the HTTR has been performed and the nuclear design shows upgraded performance of the reactor compared with the HTTR.

Oral presentation

A Basic study for the low-level radioactive liquid solidification by using geopolymer method

Kadota, Hirofumi*; Atarashi, Daiki*; Sakai, Etsuo*; Horiguchi, Kenichi

no journal, , 

no abstracts in English

24 (Records 1-20 displayed on this page)