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Journal Articles

Development of spin-contrast-variation neutron powder diffractometry for extracting the structure factor of hydrogen atoms

Miura, Daisuke*; Kumada, Takayuki; Sekine, Yurina; Motokawa, Ryuhei; Nakagawa, Hiroshi; Oba, Yojiro; Ohara, Takashi; Takata, Shinichi; Hiroi, Kosuke; Morikawa, Toshiaki*; et al.

Journal of Applied Crystallography, 54(2), p.454 - 460, 2021/04

 Times Cited Count:0 Percentile:0.02(Chemistry, Multidisciplinary)

We developed a spin-contrast-variation neutron powder diffractometry technique that extracts the structure factor of hydrogen atoms, namely, the contribution of hydrogen atoms to a crystal structure factor. Crystals of L-glutamic acid were dispersed in a dpolystyrene matrix containing 4-methacryloyloxy-2,2,6,6,-tetramethyl-1-piperidinyloxy (TEMPO methacrylate) to polarize their proton spins dynamically. The intensities of the diffraction peaks of the sample changed according to the proton polarization, and the structure factor of the hydrogen atoms was extracted from the proton-polarization dependent intensities. This technique is expected to enable analyses of the structures of hydrogen-containing materials that are difficult to determine with conventional powder diffractometry.

Journal Articles

Progress report of Japanese simulation research projects using the high-performance computer system Helios in the International Fusion Energy Research Centre

Ishizawa, Akihiro*; Idomura, Yasuhiro; Imadera, Kenji*; Kasuya, Naohiro*; Kanno, Ryutaro*; Satake, Shinsuke*; Tatsuno, Tomoya*; Nakata, Motoki*; Nunami, Masanori*; Maeyama, Shinya*; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 92(3), p.157 - 210, 2016/03

The high-performance computer system Helios which is located at The Computational Simulation Centre (CSC) in The International Fusion Energy Research Centre (IFERC) started its operation in January 2012 under the Broader Approach (BA) agreement between Japan and the EU. The Helios system has been used for magnetised fusion related simulation studies in the EU and Japan and has kept high average usage rate. As a result, the Helios system has contributed to many research products in a wide range of research areas from core plasma physics to reactor material and reactor engineering. This project review gives a short catalogue of domestic simulation research projects. First, we outline the IFERC-CSC project. After that, shown are objectives of the research projects, numerical schemes used in simulation codes, obtained results and necessary computations in future.

Journal Articles

Evaluation of HLW glass dissolution/alteration kinetics by using micro-channel flow-through test method; Initial glass dissolution rate as a function of pH and temperature

Inagaki, Yaohiro*; Sakatani, Keiichi*; Yamamura, Yuki*; Mitsui, Seiichiro; Noshita, Kenji*; Miura, Yoshiyuki*; Kanehira, Norio*; Ochi, Eiji*; Mukunoki, Atsushi*; Chiba, Tamotsu*

Dai-7-Kai Saishori, Risaikuru Bukai Semina Tekisuto, p.136 - 137, 2011/01

Conventional static test methods are not appropriate to evaluate glass dissolution behavior at an arbitrarily-fixed condition due to compositional change of the solution with glass dissolution. In this study, we applied a newly-devised micro-channel flow-through test method to measurement of the initial dissolution rates of Japanese simulated waste glasses, JAEA-P0798 and JNFL-KMOC, at arbitrarily-fixed conditions and we evaluated temperature and pH dependence of glass dissolution. The results showed that the initial dissolution rate increased with temperature and had "V-shaped" pH dependence at each temperature.

Journal Articles

First test results for the ITER central solenoid model coil

Kato, Takashi; Tsuji, Hiroshi; Ando, Toshinari; Takahashi, Yoshikazu; Nakajima, Hideo; Sugimoto, Makoto; Isono, Takaaki; Koizumi, Norikiyo; Kawano, Katsumi; Oshikiri, Masayuki*; et al.

Fusion Engineering and Design, 56-57, p.59 - 70, 2001/10

 Times Cited Count:17 Percentile:76.5(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Progress of the ITER central solenoid model coil programme

Tsuji, Hiroshi; Okuno, Kiyoshi*; Thome, R.*; Salpietro, E.*; Egorov, S. A.*; Martovetsky, N.*; Ricci, M.*; Zanino, R.*; Zahn, G.*; Martinez, A.*; et al.

Nuclear Fusion, 41(5), p.645 - 651, 2001/05

 Times Cited Count:55 Percentile:84.47(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Prototype tokamak fusion power reactor based on SiC/SiC composite material, focussing on easy maintenance

Nishio, Satoshi; Ueda, Shuzo; Kurihara, Ryoichi; Kuroda, Toshimasa*; Miura, H.*; Sako, Kiyoshi*; Takase, Kazuyuki; Seki, Yasushi; Adachi, Junichi*; Yamazaki, Seiichiro*; et al.

Fusion Engineering and Design, 48(3-4), p.271 - 279, 2000/09

 Times Cited Count:16 Percentile:72(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Void fraction effects on stability in cable-in-conduit conductor for varying field due to plasma disruption

Terasawa, Atsumi; Miura, Yushi; Ando, Toshinari; Nozawa, Masanobu*; Isono, Takaaki; Takaya, Yoshiyuki*; Tsuji, Hiroshi; Shimamoto, Susumi

ICEC16/ICMC Proceedings, p.1265 - 1268, 1996/00

no abstracts in English

Oral presentation

Study on flow-induced-vibration evaluation of large-diameter pipings in a sodium-cooled fast reactor, 5; LDV measurement of flow in an elbow installed in a 1/10-scale hot leg model

Iwamoto, Yukiharu*; Minamiura, Hirotaka*; Aoyama, Yoshiyuki*; Murakami, Koichi*; Yamano, Hidemasa; Kotake, Shoji

no journal, , 

Velocity distributions have been measured by an LDV under 50000 of Reynolds number to grasp the flow characteristics in a hot-leg piping with a single elbow.

Oral presentation

Temporal facility radiation control activities in JAEA research reactor plants under ascended radiation levels due to the accident of Fukushima Daiichi Nuclear Plants

Irokawa, Hiroyuki; Hamazaki, Masaaki; Ishida, Keiichi; Miura, Yoshiyuki; Iwasa, Atsutoshi; Kano, Yutaka; Mikami, Satoshi; Takashima, Hideki; Hitomi, Junichi

no journal, , 

no abstracts in English

Oral presentation

The Training for young educators to learn the correct understanding about handling of radioactive materials and radiation

Usui, Toshihide; Nakayama, Naoto; Iwasa, Atsutoshi; Miura, Yoshiyuki; Ishida, Keiichi; Irokawa, Hiroyuki; Hamazaki, Masaaki; Okawa, Yasuhisa; Iwai, Ryo

no journal, , 

no abstracts in English

Oral presentation

Passive siphon breaker for the cooling water in Joyo spent fuel pool

Ishimaru, Masaru; Maeda, Shigetaka; Miura, Yoshiyuki; Suzuki, Toshiaki

no journal, , 

no abstracts in English

Oral presentation

Maintenance management of fuel handling and storage system in the experimental fast reactor "JOYO"

Kawakami, Shodai; Suzuki, Toshiaki; Takahashi, Tsuyoshi*; Fujinaka, Hideaki; Miura, Yoshiyuki

no journal, , 

no abstracts in English

12 (Records 1-12 displayed on this page)
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