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Journal Articles

A Framework for limited use of high-dose areas following the Fukushima nuclear accident

Saito, Yoshika*; Ito, Naomi*; Abe, Toshiki*; Yamamoto, Chika*; Matsumoto, Chihiro*; Zhao, T.*; Moriyama, Nobuaki*; Yoshimura, Kazuya; Sanada, Yukihisa; Tsubokura, Masaharu*

Journal of Radiological Protection, 46(1), p.013502_1 - 013502_8, 2026/03

 Times Cited Count:0 Percentile:0.00(Environmental Sciences)

Journal Articles

Evaluation of vortex gas entrainment phenomena

Ito, Kei*; Matsushita, Kentaro; Ezure, Toshiki; Tanaka, Masaaki; Odaira, Naoya*; Ito, Daisuke*; Saito, Yasushi*

Nihon Kikai Gakkai 2025-Nendo Nenji Taikai Koen Rombunshu (Internet), 5 Pages, 2025/09

The estimation of entrained gas flow rate by a bathtub vortex is important in terms of a possibility to causes the performance degradation when the entrained bubbles are mixed into fluid machineries, e.g. pumps. In this study, to confirm the applicability of a model based on circulating annular flow model proposed by the authors, entrained gas flow rate is evaluated using the liquid velocity distribution around free surface dent of vortex (gas core), obtained by CFD data. As a result, it was indicated that it would be possible to evaluate the gas entrainment flow rate by setting an appropriate evaluation region.

Journal Articles

Multiscale observation of nano-oxide particles in oxide-dispersion-strengthened Cu alloys

Saito, Toshiki*; Yu, H.*; Gao, Z.*; Inoue, Koji*; Kondo, Sosuke*; Kasada, Ryuta*; Nagai, Yasuyoshi*; Oba, Yojiro*; Hiroi, Kosuke

Journal of Alloys and Compounds, 983, p.173852_1 - 173852_12, 2024/05

 Times Cited Count:10 Percentile:73.01(Chemistry, Physical)

Journal Articles

CFD-based analysis and experimental study on gas entrainment phenomenon due to free surface vortex

Song, K.*; Ito, Kei*; Ito, Daisuke*; Odaira, Naoya*; Saito, Yasushi*; Matsushita, Kentaro; Ezure, Toshiki; Tanaka, Masaaki

Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 10 Pages, 2023/05

Gas entrainment (GE) phenomena caused by a free surface vortex may cause the disturbance in core power of sodium-cooled fast reactor (SFR). For this reason, the entrained gas flow rate by the GE should be evaluated accurately for the practical safety design of SFRs. In this study, for the purpose of examining the applicability of CFD for the accurate evaluation of GE phenomena, a CFD is applied to the simulation of the free surface vortex and accompanied GE phenomena in a cylindrical vessel with a suction pipe, and the CFD results and the experimental data of the GE are compared. As a result, the CFD and experiments show similar two-phase flow pattern inside the suction pipe, and the shape of the gas core at the free surface is also very similar. Therefore, it is confirmed that the CFD can predict the GE phenomena triggered by a free surface vortex properly and accurately within the acceptable error range.

Journal Articles

Sodium-cooled Fast Reactors

Ohshima, Hiroyuki; Morishita, Masaki*; Aizawa, Kosuke; Ando, Masanori; Ashida, Takashi; Chikazawa, Yoshitaka; Doda, Norihiro; Enuma, Yasuhiro; Ezure, Toshiki; Fukano, Yoshitaka; et al.

Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07

This book is a collection of the past experience of design, construction, and operation of two reactors, the latest knowledge and technology for SFR designs, and the future prospects of SFR development in Japan. It is intended to provide the perspective and the relevant knowledge to enable readers to become more familiar with SFR technology.

Journal Articles

Evaluation of gas entrainment flow rate by free surface vortex

Torikawa, Tomoaki*; Odaira, Naoya*; Ito, Daisuke*; Ito, Kei*; Saito, Yasushi*; Matsushita, Kentaro; Ezure, Toshiki; Tanaka, Masaaki

Konsoryu, 36(1), p.63 - 69, 2022/03

On free surface of a sodium cooled fast reactor, gas entrainment can be caused by free surface vortices, which may result in disturbance in core power. It is important to develop an evaluation model to predict accurately entrained gas flow rate. In this study, entrained gas flow rate a simple gas entrainment experiment is conducted with focusing on effect of pressure difference between upper and lower tanks. Pressure difference between upper and lower tanks are controlled by changing gas pressure in lower tank. As a result, it is confirmed that the entrained gas flow rate increases with increasing pressure difference between upper and lower tanks. By visualization of swirling annular flow in suction pipe, it is also observed that pressure drop in suction pipe increases with increase in entrained gas flow rate, which implies that entrained gas flow rate can be predicted by evaluation model based on pressure drop in swirling annular flow region.

Journal Articles

Distinct variation of electronic states due to annealing in $$T'$$-type La$$_{1.8}$$Eu$$_{0.2}$$CuO$$_{4}$$ and Nd$$_{2}$$CuO$$_{4}$$

Asano, Shun*; Ishii, Kenji*; Matsumura, Daiju; Tsuji, Takuya; Kudo, Kota*; Taniguchi, Takanori*; Saito, Shin*; Sunohara, Toshiki*; Kawamata, Takayuki*; Koike, Yoji*; et al.

Physical Review B, 104(21), p.214504_1 - 214504_7, 2021/12

 Times Cited Count:2 Percentile:8.04(Materials Science, Multidisciplinary)

Journal Articles

Study on evaluation method for entrained gas flow rate by free surface vortex

Ito, Kei*; Ito, Daisuke*; Saito, Yasushi*; Ezure, Toshiki; Matsushita, Kentaro; Tanaka, Masaaki; Imai, Yasutomo*

Proceedings of 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18) (USB Flash Drive), p.6632 - 6642, 2019/08

In this paper, a mechanistic model is proposed to calculate the entrained gas flow rate by a free surface vortex. The model contains the theoretical equation of transient gas core elongation and the empirical equation of critical gas core length for gas bubble detachment. Based on those two equations, the entrained gas flow rate is calculated as the portion of the gas core elongated beyond the critical gas core length per unit time. Then, the mechanistic model was applied to the calculation of the entrained gas flow rate in a simple water experiment. As a result, it is confirmed that the entrained gas flow rate grows rapidly when the liquid (water) flow rate, which determine the strength of a free surface vortex, exceeds a certain threshold value.

Journal Articles

Atmospheric modeling of $$^{137}$$Cs plumes from the Fukushima Daiichi Nuclear Power Plant; Evaluation of the model intercomparison data of the Science Council of Japan

Kitayama, Kyo*; Morino, Yu*; Takigawa, Masayuki*; Nakajima, Teruyuki*; Hayami, Hiroshi*; Nagai, Haruyasu; Terada, Hiroaki; Saito, Kazuo*; Shimbori, Toshiki*; Kajino, Mizuo*; et al.

Journal of Geophysical Research; Atmospheres, 123(14), p.7754 - 7770, 2018/07

 Times Cited Count:29 Percentile:63.71(Meteorology & Atmospheric Sciences)

We compared seven atmospheric transport model results for $$^{137}$$Cs released during the Fukushima Daiichi Nuclear Power Plant accident. All the results had been submitted for a model intercomparison project of the Science Council of Japan in 2014. We assessed model performance by comparing model results with observed hourly atmospheric concentrations of $$^{137}$$Cs, focusing on nine plumes over the Tohoku and Kanto regions. The results showed that model performance for $$^{137}$$Cs concentrations was highly variable among models and plumes. We also assessed model performance for accumulated $$^{137}$$Cs deposition. Simulated areas of high deposition were consistent with the plume pathways, though the models that best simulated $$^{137}$$Cs concentrations were different from those that best simulated deposition. The ensemble mean of all models consistently reproduced $$^{137}$$Cs concentrations and deposition well, suggesting that use of a multimodel ensemble results in more effective and consistent model performance.

Journal Articles

Research and development on waste management for the Fukushima Daiichi NPS by JAEA

Koma, Yoshikazu; Ashida, Takashi; Meguro, Yoshihiro; Miyamoto, Yasuaki; Sasaki, Toshiki; Yamagishi, Isao; Kameo, Yutaka; Terada, Atsuhiko; Hiyama, Toshiaki; Koyama, Tomozo; et al.

Proceedings of International Nuclear Fuel Cycle Conference; Nuclear Energy at a Crossroads (GLOBAL 2013) (CD-ROM), p.736 - 743, 2013/09

Fukushima Daiichi Nuclear Power Station (F1NPS), TEPCO, was severely damaged with the hydrogen explosions caused by losing their cooling functions due to the earthquake and the tsunami occurred on March 11, 2011. Radioactive wastes generated from the current FINPS and future their decommission and demolition are greater huge amount than those from general reactors and nuclear fuel facilities. Toward accomplishing safe and reasonable management of the wastes, great effort of R&Ds has been strongly required and performed in bringing together the knowledge and experience of all of Japan. This report outlines the current status of the R&Ds performed in JAEA.

Journal Articles

Report of the Special Symposium on the Transport and Diffusion of Contaminants from the Fukushima Dai-ichi Nuclear Power Plant; Present status and future directions

Kondo, Hiroaki*; Yamada, Tetsuji*; Chino, Masamichi; Iwasaki, Toshiki*; Katata, Genki; Maki, Takashi*; Saito, Kazuo*; Terada, Hiroaki; Tsuruta, Haruo*

Tenki, 60(9), p.723 - 729, 2013/09

AA2013-0745.pdf:0.51MB

no abstracts in English

Journal Articles

Super-parallel simulation systems for sophisticated radiation therapy

Saito, Kimiaki; Saito, Hidetoshi*; Kunieda, Etsuo*; Narita, Yuichiro*; Myojoyama, Atsushi*; Fujisaki, Tatsuya*; Kawase, Takatsugu*; Kaneko, Katsutaro*; Ozaki, Masahiro*; Deloar, H. M.*; et al.

Joho Shori, 48(10), p.1081 - 1088, 2007/10

no abstracts in English

Journal Articles

Applicability of coal ash (fly ash) to high strength shotcrete

Orukawa, Go; Kojima, Wataru; Shirato, Nobuaki*; Saito, Toshiki*

Konkurito Kogaku Nenji Rombunshu (DVD-ROM), 28(1), p.1637 - 1642, 2006/00

no abstracts in English

Journal Articles

Feasilibity study of the K900 superconducting AVF cyclotron for materials science and biotechnology

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

Proceedings of 1st Annual Meeting of Particle Accelerator Society of Japan and 29th Linear Accelerator Meeting in Japan, p.643 - 645, 2004/08

A superconducting AVF cyclotron with a bending limit of 900 MeV and a focusing limit of 300 MeV is being designed to meet the requirements for the research in materials science and biotechnology at TIARA facility of JAERI. The spiral-sector shape of the cyclotron magnet has been optimized for acceleration of a 300 MeV proton to produce sufficient focusing forces in an extraction region. An energy range of the superconducting AVF cyclotron overlaps with that of the present K110 JAERI AVF cyclotron. Characteristics of a resonator for the superconducting AVF cyclotron have been investigated using the MAFIA code. An acceleration voltage in a frequency range of 24 to 64 MHz can be produced by the resonator with a $$lambda$$/2 excitation mode.

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

Journal Articles

Prepulse effects on the interaction of intense femtosecond laser pulses with high-Z solids

Zhidkov, A. G.; Sasaki, Akira; Utsumi, Takayuki*; Fukumoto, Ichiro; Tajima, Toshiki; Saito, Fumikazu*; Hironaka, Yoichiro*; Nakamura, Kazutaka*; Kondo, Kenichi*; Yoshida, Masataka*

Physical Review E, 62(5), p.7232 - 7240, 2000/11

 Times Cited Count:52 Percentile:85.28(Physics, Fluids & Plasmas)

no abstracts in English

JAEA Reports

Evaluation on materials performance of Hastelloy alloy XR for HTTR uses, 6; Tensile and creep properties of heat exchanger tube base materials and its welded-joints

Watanabe, Katsutoshi; Shindo, Masami; Nakajima, Hajime; Koikegami, Hajime*; Higuchi, Makoto*; Nakanishi, Tsuneo*; Sahira, Kensho*; Marushichi, Koki*; Takeiri, Toshiki*; Saito, Teiichiro*; et al.

JAERI-Research 97-009, 62 Pages, 1997/02

JAERI-Research-97-009.pdf:4.82MB

no abstracts in English

JAEA Reports

Evaluation on materials performance of hastelloy alloy XR for HTTR uses-3; Manufacture of filler metal and its weldability

Watanabe, Katsutoshi; Nakajima, Hajime; Saito, Teiichiro*; Takatsu, Tamao*; Koikegami, Hajime*; Higuchi, Makoto*; Nakanishi, Tsuneo*; Sahira, Kensho*; Marushichi, Koki*; Takeiri, Toshiki*

JAERI-Research 94-046, 50 Pages, 1994/12

JAERI-Research-94-046.pdf:2.23MB

no abstracts in English

Journal Articles

Development of a filler metal for Hastelloy Alloy XR welded-structures for High Temperature Engineering Test Reactor application

Watanabe, Katsutoshi; Nakajima, Hajime; Sahira, Kensho*; Marushichi, Koki*; Takeiri, Toshiki*; Saito, Teiichiro*; Takatsu, Tamao*; Nakanishi, Tsuneo*; Koikegami, Hajime*; Higuchi, Makoto*

Proc. of the 2nd JAERI Symp. on HTGR Technologies; Oct. 21$$sim$$23,1992,Oarai,Japan (JAERI-M 92-215), p.560 - 574, 1993/01

no abstracts in English

Journal Articles

Development of hastelloy alloy XR filler metal lowered weld cracking susceptibility

Watanabe, Katsutoshi; Nakajima, Hajime; Sahira, Kensho*; Marushichi, Koki*; Takeiri, Toshiki*; Saito, Teiichiro*; Takatsu, Tamao*; Nakanishi, Tsuneo*; Koikegami, Hajime*; Higuchi, Makoto*

Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 33(2), p.227 - 242, 1992/00

no abstracts in English

37 (Records 1-20 displayed on this page)