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Journal Articles

Tracer diffusion coefficient measurements on NASICON-type Lithium-ion conductor LAGP using neutron radiography between 25$$^{circ}$$C and 500$$^{circ}$$C

Takagi, Honoka*; Yabutsuka, Takeshi*; Hayashida, Hirotoshi*; Song, F.; Kai, Tetsuya; Shinohara, Takenao; Kurita, Keisuke; Iikura, Hiroshi; Yamamoto, Norio*; Nakajima, Minoru*; et al.

Solid State Ionics, 417, p.116716_1 - 116716_7, 2024/12

 Times Cited Count:3 Percentile:23.65(Chemistry, Physical)

Journal Articles

Reactor physics experiment in a graphite-moderation system for HTGR

Fukaya, Yuji; Goto, Minoru; Nakagawa, Shigeaki; Nakajima, Kunihiro*; Takahashi, Kazuki*; Sakon, Atsushi*; Sano, Tadafumi*; Hashimoto, Kengo*

EPJ Web of Conferences, 247, p.09017_1 - 09017_8, 2021/02

The Japan Atomic Energy Agency (JAEA) started the Research and Development (R&D) to improve nuclear prediction techniques for High Temperature Gas-cooled Reactors (HTGRs). The objectives are to introduce a generalized bias factor method to avoid full mock-up experiment for the first commercial HTGR and to introduce reactor noise analysis to High Temperature Engineering Test Reactor (HTTR) experiment to observe subcriticality. To achieve the objectives, the reactor core of graphite-moderation system named B7/4"G2/8"p8EUNU+3/8"p38EU(1) was newly composed in the B-rack of Kyoto University Critical Assembly (KUCA). The core is composed of the fuel assembly, driver fuel assembly, graphite reflector, and polyethylene reflector. The fuel assembly is composed of enriched uranium plate, natural uranium plate and graphite plates to realize the average fuel enrichment of HTTR and it's spectrum. However, driver fuel assembly is necessary to achieve the criticality with the small-sized core. The core plays a role of the reference core of the bias factor method, and the reactor noise was measured to develop the noise analysis scheme. In this study, the overview of the criticality experiments is reported. The reactor configuration with graphite moderation system is rare case in the KUCA experiments, and this experiment is expected to contribute not only for an HTGR development but also for other types of a reactor in the graphite moderation system such as a molten salt reactor development.

Journal Articles

Emergent spin-1 Haldane gap and ferroelectricity in a frustrated spin-$$frac{1}{2}$$ ladder

Ueda, Hiroshi*; Onoda, Shigeki*; Yamaguchi, Yasuhiro*; Kimura, Tsuyoshi*; Yoshizawa, Daichi*; Morioka, Toshiaki*; Hagiwara, Masayuki*; Hagihara, Masato*; Soda, Minoru*; Masuda, Takatsugu*; et al.

Physical Review B, 101(14), p.140408_1 - 140408_6, 2020/04

 Times Cited Count:6 Percentile:24.98(Materials Science, Multidisciplinary)

Journal Articles

Reactor physics experiment in a graphite-moderation system for HTGR

Fukaya, Yuji; Goto, Minoru; Nakagawa, Shigeaki; Nakajima, Kunihiro*; Takahashi, Kazuki*; Sakon, Atsushi*; Sano, Tadafumi*; Hashimoto, Kengo*

Proceedings of International Conference on the Physics of Reactors; Transition To A Scalable Nuclear Future (PHYSOR 2020) (USB Flash Drive), 8 Pages, 2020/03

The Japan Atomic Energy Agency (JAEA) started the Research and Development (R&D) to improve nuclear prediction techniques for High Temperature Gas-cooled Reactors (HTGRs). The objectives are to introduce a generalized bias factor method to avoid full mock-up experiment for the first commercial HTGR and to introduce reactor noise analysis to High Temperature Engineering Test Reactor (HTTR) experiment to observe subcriticality. To achieve the objectives, the reactor core of graphite-moderation system named B7/4"G2/8"p8EUNU+3/8"p38EU(1) was newly composed in the B-rack of Kyoto University Critical Assembly (KUCA). The core is composed of the fuel assembly, driver fuel assembly, graphite reflector, and polyethylene reflector. The fuel assembly is composed of enriched uranium plate, natural uranium plate and graphite plates to realize the average fuel enrichment of HTTR and it's spectrum. However, driver fuel assembly is necessary to achieve the criticality with the small-sized core. The core plays a role of the reference core of the bias factor method, and the reactor noise was measured to develop the noise analysis scheme. In this study, the overview of the criticality experiments is reported. The reactor configuration with graphite moderation system is rare case in the KUCA experiments, and this experiment is expected to contribute not only for an HTGR development but also for other types of a reactor in the graphite moderation system such as a molten salt reactor development.

Journal Articles

Activities for preserving information resources of Fukushima Daiichi Nuclear Power Station accident; Constructing, operating the archive and its future prospect

Hayakawa, Misa; Kumazaki, Yui; Nakajima, Hidemitsu; Yonezawa, Minoru

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 58(8), p.509 - 513, 2016/08

AA2016-0050.pdf:0.82MB

no abstracts in English

Journal Articles

Spin model of O$$_{2}$$-based magnet in a nanoporous metal complex

Soda, Minoru*; Homma, Yuki*; Takamizawa, Satoshi*; Kawamura, Seiko; Nakajima, Kenji; Masuda, Takatsugu*

Journal of the Physical Society of Japan, 85(3), p.034717_1 - 034717_9, 2016/03

 Times Cited Count:2 Percentile:17.69(Physics, Multidisciplinary)

Inelastic neutron scattering experiments are performed on the nanoporous metal complex Cu-${{it trans}}$-1,4-cyclohexanedicarboxylic acid (Cu-CHD) adsorbing O$$_{2}$$ molecules to identify the spin model of the O$$_{2}$$-based magnet realized in the host complex. It is found that the magnetic excitations of Cu-CHDs adsorbing low- and high-concentration O$$_{2}$$ molecules are explained by different spin models, the former by spin dimers and the latter by spin trimers. By using the obtained parameters and by assuming that the levels of the group of the highest energy states are reduced because of the nonnegligible spin dependence of the molecular potential of oxygen, the magnetization curves are explained quantitatively.

Journal Articles

Spin-nematic interaction in the multiferroic compound Ba$$_{2}$$CoGe$$_{2}$$O$$_{7}$$

Soda, Minoru*; Matsumoto, Masashige*; M$"a$nsson, M.*; Kawamura, Seiko; Nakajima, Kenji; Shiina, Ryosuke*; Masuda, Takatsugu*

Physical Review Letters, 112(12), p.127205_1 - 127205_5, 2014/03

 Times Cited Count:46 Percentile:85.18(Physics, Multidisciplinary)

We demonstrate the existence of the spin-nematic interactions in an easy-plane type antiferromagnet Ba$$_{2}$$CoGe$$_{2}$$O$$_{7}$$ by exploring the magnetic anisotropy and spin dynamics. The combination of neutron scattering and magnetic susceptibility measurements reveals that the origin of the in-plane anisotropy is an antiferro-type interaction of the spin-nematic operator. The relation between the nematic operator and the electric polarization in the ligand symmetry of this compound is presented. The introduction of the spinnematic interaction is useful to understand the physics of spin and electric dipole in multiferroic compounds.

Journal Articles

Study for development of the Fukushima Dai-ichi Nuclear Power Station accident archive

Nakajima, Hidemitsu; Ikeda, Kiyoshi; Yonezawa, Minoru; Itabashi, Keizo; Kiriyama, Eriko*; Iwata, Shuichi*

Joho Chishiki Gakkai-Shi, 22(4), p.344 - 353, 2012/11

BB2012-1951.pdf:2.04MB

The Library of Japan Atomic Energy Agency (JAEA) has developed the special website on Fukushima Dai-ichi Nuclear Power Station accident from April 4, 2011. This website is provided both in Japanese and English. It disseminates over 15,000 bibliographic and full-text records, such as JAEA's research results, academic journal articles, conference papers, technical reports etc. In this paper, the authors introduce the special website on Fukushima Dai-ichi Nuclear Power Station accident and discuss some challenging issues to develop archive.

Journal Articles

Introduction of useful bibliographies and resources related to the Fukushima Dai-ichi Nuclear Power Station accident through the JAEA Library

Ikeda, Kiyoshi; Yonezawa, Minoru; Nakajima, Hidemitsu

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 54(8), p.549 - 553, 2012/08

no abstracts in English

Journal Articles

Feasible evaluation of neutron capture therapy for hepatocellular carcinoma using selective enhancement of boron accumulation in tumour with intra-arterial administration of boron-entrapped water-in-oil-in-water emulsion

Yanagie, Hironobu*; Kumada, Hiroaki*; Nakamura, Takemi; Higashi, Shushi*; Ikushima, Ichiro*; Morishita, Yasuyuki*; Shinohara, Atsuko*; Fujiwara, Mitsuteru*; Suzuki, Minoru*; Sakurai, Yoshinori*; et al.

Proceedings of 14th International Congress on Neutron Capture Therapy (ICNCT-14) (CD-ROM), p.157 - 160, 2010/10

Journal Articles

Quantitative analysis of cisplatin sensitivity of human esophageal squamous cancer cell lines using in-air micro-PIXE

Tanaka, Naritake*; Kimura, Hitoshi*; Faried, A.*; Sakai, Makoto*; Sano, Takaaki*; Inose, Takanori*; Soda, Makoto*; Okada, Koji*; Nakajima, Masanobu*; Miyazaki, Tatsuya*; et al.

Cancer Science, 101(6), p.1487 - 1492, 2010/06

 Times Cited Count:13 Percentile:31.67(Oncology)

We examined the intracellular localization of cisplatin, a key chemotherapeutic agent, in esophageal cancer cell lines and determined their sensitivity to cisplatin using in-air micro-PIXE. Two human esophageal squamous cell carcinoma (ESCC) cell lines, TE-2 and TE-13, were examined for their response to cisplatin using MTT assay, flow cytometry and DNA fragmentation assays. Real-time reverse transcription-polymerase chain reaction was also used to evaluate the mRNA expression of multidrug resistance protein 2 (MRP2) in both cell lines. Platinum localizations of intracellular and intranuclear were measured using in-air micro-PIXE. TE-2 cells were more sensitive to cisplatin than TE-13 cells. The results of this study suggest that in-air micro-PIXE could be a useful quantitative method for evaluating the cisplatin sensitivity of individual cells. Finally, we speculate that MRP2 in the cell membrane may play an important role in regulating cisplatin sensitivity of ESCC cells.

Journal Articles

Evaluation of in-pile and out-of-pile stress relaxation in 316L stainless steel under uniaxial loading

Kaji, Yoshiyuki; Miwa, Yukio; Tsukada, Takashi; Kikuchi, Masahiko; Kita, Satoshi; Yonekawa, Minoru; Nakano, Junichi; Tsuji, Hirokazu; Nakajima, Hajime

Journal of Nuclear Materials, 307-311(Part1), p.331 - 334, 2002/12

 Times Cited Count:5 Percentile:33.09(Materials Science, Multidisciplinary)

Irradiation assisted stress corrosion cracking (IASCC) caused by simultaneous effects of neutron irradiation and high temperature water environments has been pointed out as one of the major concerns of in-core structural materials not only for the light water reactors (LWRs) but also for the water-cooled fusion reactor. It is necessary to evaluate precisely stress condition under irradiation environment, because stress is one of key factors on IASCC. Stress relaxation of tensile type specimens under fast neutron irradiation at 288$$^{circ}$$C has been studied for type 316L stainless steel in Japan Materials Testing Reactor (JMTR). This paper describes the in-pile and out-of-pile stress-relaxation test results of tensile type specimens for type 316L stainless steel as compared with the literature data by Foster, which were mainly obtained by bent beam specimens. Moreover these experimental results were compared with the analytical ones by using Nakagawa's model.

Journal Articles

Three-dimensional analysis on thermo-fluiddynamics in piping with WINDFLOW

Maruyama, Yu; Igarashi, Minoru; Nakamura, Naohiko; Hidaka, Akihide; Hashimoto, Kazuichiro; Sugimoto, Jun; Nakajima, Kengo*

JAERI-memo 08-127, p.233 - 238, 1996/06

no abstracts in English

Journal Articles

Three-dimensional thermo-fluiddynamic analysis of gas flow in straight piping with WINDFLOW code

Maruyama, Yu; Igarashi, Minoru*; Nakamura, Naohiko; Hidaka, Akihide; Hashimoto, Kazuichiro; Sugimoto, Jun; Nakajima, Kengo*

Proc. of ASME$$cdot$$JSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 1(PART B), p.997 - 1008, 1996/00

no abstracts in English

Journal Articles

Research and development on materials as base technology in nuclear applications

Kondo, Tatsuo; Hishinuma, Akimichi; Noda, Kenji; Eto, Motokuni; Tsuji, Hirokazu; Nakajima, Hajime; Kiuchi, Kiyoshi; Ono, Hideo; Ogawa, Toru; Omichi, Hideki; et al.

Genshiryoku Kogyo, 39(8), p.1 - 80, 1993/08

no abstracts in English

JAEA Reports

Facility for stress corrosion cracking test of irradiated material in high temperature water

Tsukada, Takashi; Shiba, Kiyoyuki; G.E.C.Bell*; Nakajima, Hajime; Kizaki, Minoru; Omi, Masao; Sudo, Kenji; Goto, Ichiro

JAERI-M 92-081, 27 Pages, 1992/06

JAERI-M-92-081.pdf:1.73MB

no abstracts in English

Journal Articles

Post irradiation test facilities for irradiation assisted stress corrosion cracking research

Tsukada, Takashi; Shiba, Kiyoyuki; Omi, Masao; Kizaki, Minoru; ; Nakajima, Hajime

Proc. of the 3rd Asian Symp. on Research Reactor, 8 Pages, 1991/00

no abstracts in English

Oral presentation

Study of complex magnetic structures in frustrated magnets by means of polarized neutrons

Kakurai, Kazuhisa; Wakimoto, Shuichi; Matsuda, Masaaki*; Ishiwata, Shintaro*; Okuyama, Daisuke*; Taguchi, Yasujiro*; Tokura, Yoshiki*; Nishi, Masakazu*; Nakajima, Taro*; Mitsuda, Setsuo*; et al.

no journal, , 

Oral presentation

R&D to improve accuracy of nuclear prediction for HTGR, 1; Experiment of first mock-up reactor with graphite system in KUCA

Fukaya, Yuji; Goto, Minoru; Nakagawa, Shigeaki; Nakajima, Kunihiro*; Takahashi, Kazuki*; Sakon, Atsushi*; Hashimoto, Kengo*; Sano, Tadafumi*

no journal, , 

To improve accuracy of nuclear prediction for HTGR, we performed the critical experiment and reactor noise measurement to obtain HTGR nuclear characteristics by configuring the graphite moderation system mock-up core at the solid moderator rack (B rack) in Kyoto University Critical Assembly (KUCA). This report states the overview of the criticality experiment and future perspective of this R&D.

Oral presentation

An Attempt to archive the information on the Fukushima Dai-ichi Nuclear Power Station accident; Collecting and disseminating the related information at the Library of Japan Atomic Energy Agency

Nakajima, Hidemitsu; Ikeda, Kiyoshi; Yonezawa, Minoru; Itabashi, Keizo

no journal, , 

The Library of Japan Atomic Energy Agency (JAEA) has developed the special website on Fukushima Dai-ichi Nuclear Power Station accident from April 4, 2011. This website disseminates over 11,000 bibliographic and full-text records, such as JAEA's research results, academic journal articles, conference papers, technical reports and web information. Through this activity, we found several challenging issues. First, to organize information in a systematic manner is important, and subject and bibliographic control leads to the improvement of user-friendliness. Second, information on the internet has a specific problem such as access URLs might be changed or deleted. In order to ensure accessibility of information source, it is desirable that the public institutions crawl internet websites and preserve original information. In this presentation, we introduce the special website on Fukushima Dai-ichi Nuclear Power Station accident and discuss some challenging issues to develop archive.

Oral presentation

Archival activities for the technical information on the accident of Fukushima Daiichi Nuclear Power Stations and the suggestion to the information management on radioactive waste management

Igarashi, Hiroshi; Ikeda, Kiyoshi; Yonezawa, Minoru; Nakajima, Hidemitsu

no journal, , 

Since the nuclear accident of Fukushima Daiichi Nuclear Power Stations (Fukushima nuclear accident) which occurred in the Great East Japan Earthquake on March 11th 2011, a great deal of information on the accident and the response has been disseminated from the government, utilities and related research institutes. To put the information into good account in the radiation control in the affected area, decommissioning the reactors, environmental remediation, recurrence prevention, etc., the appropriate conservation and succession of the information which is referred to as archives hereinafter, is important. The activities of archives on the information and knowledge are essential as assets to be shared and utilized not only domestically but also internationally. On the other hand, the conservation of the information on radioactive waste management until final disposal has been also considered to be important. In this presentation, the archival activities on the Fukushima nuclear accident are reported with a focus on the Fukushima Archive system developed by the JAEA. On the basis of the archival activities investigated, lessons learned are discussed toward the information management on radioactive waste management.

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