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Journal Articles

Uranium (VI) sorption on illite under varying carbonate concentrations; Batch experiments, modeling, and cryogenic time-resolved laser fluorescence spectroscopy study

Mei, H.; Aoyagi, Noboru; Saito, Takumi*; Kozai, Naofumi; Sugiura, Yuki; Tachi, Yukio

Applied Geochemistry, 136, p.105178_1 - 105178_8, 2022/01

Journal Articles

Surface complexation of Ca and competitive sorption of divalent cations on montmorillonite under alkaline conditions

Sugiura, Yuki; Ishidera, Takamitsu; Tachi, Yukio

Applied Clay Science, 200, p.105910_1 - 105910_10, 2021/01

 Times Cited Count:2 Percentile:0.03(Chemistry, Physical)

Journal Articles

Sorption behavior of selenide on montmorillonite

Sugiura, Yuki; Tomura, Tsutomu*; Ishidera, Takamitsu; Doi, Reisuke; Francisco, P. C. M.; Shiwaku, Hideaki; Kobayashi, Toru; Matsumura, Daiju; Takahashi, Yoshio*; Tachi, Yukio

Journal of Radioanalytical and Nuclear Chemistry, 324(2), p.615 - 622, 2020/05

 Times Cited Count:1 Percentile:0.01(Chemistry, Analytical)

JAEA Reports

Development of JAEA sorption database (JAEA-SDB); Update of sorption/QA data in FY2019

Sugiura, Yuki; Suyama, Tadahiro*; Tachi, Yukio

JAEA-Data/Code 2019-022, 40 Pages, 2020/03

JAEA-Data-Code-2019-022.pdf:2.22MB

Sorption behavior of radionuclides (RNs) in buffer materials, rocks and cementitious materials is one of the key processes in a safe geological disposal. This report focuses on updating of JAEA sorption database (JAEA-SDB) as a basis of integrated approach for the performance assessment (PA)-related distribution coefficient (K$$_{rm d}$$) setting and development of mechanistic sorption models. K$$_{rm d}$$ data and their quality assurance (QA) results were updated by focusing on the following systems as potential needs extracted from our recent activities on the K$$_{rm d}$$ setting and development of mechanistic models, i.e., clay minerals, sedimentary rocks and cementitious materials. As a result, 6,702 K$$_{rm d}$$ data from 60 references were added and the total number of K$$_{rm d}$$ values in JAEA-SDB reached 69,679. The QA/classified K$$_{rm d}$$ data reached about 72% for all K$$_{rm d}$$ data in JAEA-SDB.

JAEA Reports

Development of JAEA sorption database (JAEA-SDB); Update of sorption/QA data in FY2017

Sugiura, Yuki; Suyama, Tadahiro*; Tachi, Yukio

JAEA-Data/Code 2017-016, 54 Pages, 2018/03

JAEA-Data-Code-2017-016.pdf:2.06MB

Sorption and diffusion of radionuclides in buffer materials (bentonites), rocks and cementitious materials are the key processes in the safe geological disposal of radioactive waste, because migration of radionuclides in these barrier materials is expected to be diffusion-controlled and retarded by sorption processes. It is therefore necessary to understand the sorption and diffusion processes and develop databases compiling reliable data and mechanistic/predictive models, so that reliable parameters can be set under a variety of geochemical conditions relevant to performance assessment (PA). The present report focuses on updating of the sorption database (JAEA-SDB) as basis of integrated approach for PA-related K$$_{d}$$ setting and mechanistic sorption model development. This includes an overview of database structure and contents. K$$_{d}$$ data and their QA results are updated by focusing our recent activities on the K$$_{d}$$ setting and mechanistic model development. As a result, 4,256 K$$_{d}$$ data from 30 references were added, total number of K$$_{d}$$ values in the JAEA-SDB reached about 63,000. The QA/classified K$$_{d}$$ data reached about 69% for all K$$_{d}$$ data in JAEA-SDB. The updated JAEA-SDB is expected to make it possible to obtain quick overview of the available data, and to have suitable access to the respective data for PA-related K$$_{d}$$ setting in effective, traceable and transparent manner.

Journal Articles

Journal Articles

Rational design of DNA sequence-specific zinc fingers

Kono, Hidetoshi; Imanishi, Miki*; Negi, Shigeru*; Tatsutani, Kazuya*; Sakaeda, Yui*; Hashimoto, Ayaka*; Nakayama, Chie*; Futaki, Shiro*; Sugiura, Yukio*

FEBS Letters, 586(6), p.918 - 923, 2012/03

 Times Cited Count:5 Percentile:17.5(Biochemistry & Molecular Biology)

Journal Articles

IFMIF/EVEDA lithium test loop; Design and fabrication technology of target assembly as a key component

Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Nakamura, Kazuyuki; Ida, Mizuho; Watanabe, Kazuyoshi; Kanemura, Takuji; Wakai, Eiichi; Horiike, Hiroshi*; Yamaoka, Nobuo*; et al.

Nuclear Fusion, 51(12), p.123008_1 - 123008_12, 2011/12

 Times Cited Count:36 Percentile:84.88(Physics, Fluids & Plasmas)

The Engineering Validation and Engineering Design Activity (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF) is proceeded as one of the ITER Broader Approach (BA) activities. The EVEDA Li test loop (ELTL) is aimed at validating stability of the Li target and feasibility of a Li purification system as the key issues. In this paper, the design of the ELTL especially of a target assembly in which the Li target is produced by the contraction nozzle is presented.

Journal Articles

Present status of Japanese tasks for lithium target facility under IFMIF/EVEDA

Nakamura, Kazuyuki; Furukawa, Tomohiro; Hirakawa, Yasushi; Kanemura, Takuji; Kondo, Hiroo; Ida, Mizuho; Niitsuma, Shigeto; Otaka, Masahiko; Watanabe, Kazuyoshi; Horiike, Hiroshi*; et al.

Fusion Engineering and Design, 86(9-11), p.2491 - 2494, 2011/10

 Times Cited Count:10 Percentile:65.84(Nuclear Science & Technology)

In IFMIF/EVEDA, tasks for lithium target system are shared to 5 validation tasks (LF1-5) and a design task (LF6). The purpose of LF1 task is to construct and operate the EVEDA lithium test loop, and JAEA has a main responsibility to the performance of the Li test loop. LF2 is a task for the diagnostics of the Li test loop and IFMIF design. Basic research for the diagnostics equipment has been completed, and the construction for the Li test loop will be finished before March in 2011. LF4 is a task for the purification systems with nitrogen and hydrogen. Basic research for the purification equipment has been completed, and the construction of the nitrogen system for the Li test loop will be finished before March in 2011. LF5 is a task for the remote handling system with the target assembly. JAEA has an idea to use the laser beam for cutting and welding of the lip part of the flanges. LF6 is a task for the design of the IFMIF based on the validation experiments of LF1-5.

Journal Articles

Target system of IFMIF-EVEDA in Japanese activities

Ida, Mizuho; Fukada, Satoshi*; Furukawa, Tomohiro; Hirakawa, Yasushi; Horiike, Hiroshi*; Kanemura, Takuji*; Kondo, Hiroo; Miyashita, Makoto; Nakamura, Hiroo; Sugiura, Hirokazu*; et al.

Journal of Nuclear Materials, 417(1-3), p.1294 - 1298, 2011/10

 Times Cited Count:3 Percentile:28.8(Materials Science, Multidisciplinary)

Engineering Validation and Engineering Design Activities (EVEDA) of the International Fusion Materials Irradiation Facility (IFMIF) was started. As a Japanese activity for the target system, EVEDA Lithium Test Loop simulating hydraulic and impurity conditions of IFMIF is under design and preparation for fabrication. Feasibility of thermo-mechanical structure of the target assembly and the replaceable back-plate made of F82H (a RAFM) and 316L (a stainless steel) is a key issue. Toward final validation on the EVEDA loop, diagnostics applicable to a high-speed free-surface Li flow and hot traps to control nitrogen and hydrogen in Li are under tests. For remote handling of target assemblies and the replaceable back-plates activated up to 50 dpa/y, lip weld on 316L-316L by laser and dissimilar weld on F82H-316L are under investigation. As engineering design of the IFMIF target system, water experiments and hydraulic/thermo-mechanical analyses of the back-plate are going.

Journal Articles

Diagnostics of high-speed liquid lithium jet for IFMIF/EVEDA lithium test loop

Kanemura, Takuji; Kondo, Hiroo; Sugiura, Hirokazu*; Horiike, Hiroshi*; Yamaoka, Nobuo*; Furukawa, Tomohiro; Ida, Mizuho; Matsushita, Izuru*; Nakamura, Kazuyuki

Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 7 Pages, 2011/10

Regarding R&Ds on the International Fusion Materials Irradiation Facility (IFMIF), validation of hydraulic stability of a liquid Li jet simulating the IFMIF Li target is of crucial importance and thus, is planned to be performed using EVEDA Li test loop. This paper presents diagnostics of the Li jet to be implemented in validation tests of the jet stability. In the tests, the following physical parameters need to be measured; thickness of the jet; height, length and frequency of free-surface waves; and Li evaporation rate. A high-speed video (HSV) camera is planned to be used for understanding of detailed structure of free-surface waves, and the HSV images are to be analyzed to obtain wave velocity and frequency. To measure jet thickness and wave height, a contact-type liquid level sensor is to be used. With regard to Li evaporation rate, deposition of Li on the specimens installed near the free surface is to be measured. In addition, frequency change of a crystal quartz will be utilized.

Journal Articles

Design and construction of IFMIF/EVEDA lithium test loop

Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Ida, Mizuho; Matsushita, Izuru*; Horiike, Hiroshi*; Kanemura, Takuji; Sugiura, Hirokazu*; Yagi, Juro*; Suzuki, Akihiro*; et al.

Journal of Engineering for Gas Turbines and Power, 133(5), p.052910_1 - 052910_6, 2010/12

 Times Cited Count:7 Percentile:42.96(Engineering, Mechanical)

As a major Japanese activity for the IFMIF/EVEDA, EVEDA Li Test Loop (ELTL) to simulate hydraulic and impurity conditions of IFMIF is under design and preparation for fabrication. Feasibility of hydraulic stability of the liquid Li target and the purification systems of hot traps are major key issues to be validated. This paper presents the current status of the design and construction of the EVEDA Li Test Loop. Detail designs of the loop components such as the target assembly, tanks, an electro-magnetic pump and flow meter and a cold trap for purification system are described in addition to the flow diagnostics system and the hot traps.

Journal Articles

Engineering design and construction of IFMIF/EVEDA lithium test loop; Design and fabrication of integrated target assembly

Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Nakamura, Hiroo*; Ida, Mizuho; Watanabe, Kazuyoshi; Miyashita, Makoto*; Horiike, Hiroshi*; Yamaoka, Nobuo*; Kanemura, Takuji; et al.

Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 8 Pages, 2010/10

The Engineering Validation and Engineering Design Activity (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF) is proceeded as one of the ITER Broader Approach (BA) activities. The EVEDA Li test loop (ELTL) is aimed at validating stability of the Li target and feasibility of a Li purification system as the key issues. In this paper, the design of the ELTL especially of a target assembly in which the Li target is produced by the contraction nozzle is presented.

Journal Articles

Current status of design and construction of IFMIF/EVEDA lithium test loop

Kondo, Hiroo; Furukawa, Tomohiro; Hirakawa, Yasushi; Matsushita, Izuru*; Ida, Mizuho; Horiike, Hiroshi*; Kanemura, Takuji; Sugiura, Hirokazu*; Yagi, Juro*; Suzuki, Akihiro*; et al.

Proceedings of 18th International Conference on Nuclear Engineering (ICONE-18) (CD-ROM), 9 Pages, 2010/05

IFMIF is a neutron source aimed at producing an intense high energy neutron flux for testing candidate fusion reactor materials. Under Broader Approach activities, Engineering Validation and Engineering Design Activities (EVEDA) of IFMIF started on July 2007. Regarding to the lithium (Li) target facility, design and construction of EVEDA Li Test Loop is a major activity and is in progress. The detail design was started at the early 2009. Fabrication of the loop was started at middle of 2009, and completion is planned at the end of Feb. 2011.

Journal Articles

On-line evaluation of spatial dose-distribution by using a 15m-long plastic scintillation-fiber

Notomi, Akihiro*; Sugiura, Nobuyuki*; Ito, Tetsuo*; Imamichi, Shoji*; Torii, Tatsuo; Noma, Hiroshi*

KEK Proceedings 2008-14, p.11 - 19, 2009/01

A 15 m-long plastic scintillation fiber (PSF) detector has been applied to the on-line evaluation of spatial dose-distribution inside the room of a low power research-reactor. It was found that the present PSF detector has enough performance as the real-time measurement system which is not only quick and simple but also reliable for monitoring use in that situation. Such application may be also useful at the medical fields which routinely use radio isotopes for diagnosis purposes (such as PET facility). From the present observation, it seems that the practically-acceptable maximum limit of PSF length is at most 15 m. More than this, the severe signal reduction brings unavoidable difficulties for the following signal processing.

Journal Articles

Use of liquid helium-3 as a neutron converter for a semiconductor-based neutron detector

Nakamura, Tatsuya; Katagiri, Masaki; Aratono, Yasuyuki; Kanno, Ikuo*; Hishiki, Shigeomi*; Sugiura, Osamu*; Murase, Yasuhiro*

Nuclear Instruments and Methods in Physics Research A, 529(1-3), p.399 - 401, 2004/08

 Times Cited Count:1 Percentile:10.64(Instruments & Instrumentation)

We evaluated the neutron-detection characteristics of a cryogenic neutron detector operating at 1.6 K, which comprises a liquid helium-3 as a neutron converter and an InSb semiconductor detector. The InSb semiconductor detector detected the protons created in the nuclear reaction $$^{3}He + n rightarrow p + T$$ in the liquid helium-3, where the density of that is ~600 times larger than that of the gaseous helium-3 at room temperature.

Journal Articles

Cryogenic neutron detector by InSb semiconductor detector with high-density helium-3 gas converter

Nakamura, Tatsuya; Katagiri, Masaki; Aratono, Yasuyuki; Kanno, Ikuo*; Hishiki, Shigeomi*; Sugiura, Osamu*; Murase, Yasuhiro*

Nuclear Instruments and Methods in Physics Research A, 520(1-3), p.76 - 79, 2004/03

 Times Cited Count:8 Percentile:50.96(Instruments & Instrumentation)

The neutron-detection characteristics of a cryogenic neutron detector comprising an InSb semiconductor detector and a helium-3 gas converter were evaluated at a gas pressure of up to 12.5atm at 4.2K. The detector successfully detected stable neutrons under these conditions, where the density of the helium-3 gas is a few-hundred times higher than that at room temperature. It was found that the neutron detection efficiency was correlated with the gas pressure - even in a backward-detection configuration - in low-temperature, high-pressure helium-3.

Journal Articles

Cryogenic neutron detector comprising an InSb semiconductor detector and a supercritical helium-3 gas converter

Nakamura, Tatsuya; Katagiri, Masaki; Aratono, Yasuyuki; Kanno, Ikuo*; Hishiki, Shigeomi*; Sugiura, Osamu*; Murase, Yasuhiro*

Review of Scientific Instruments, 75(2), p.340 - 344, 2004/02

 Times Cited Count:6 Percentile:37.25(Instruments & Instrumentation)

We evaluated the neutron-detection characteristics of a proposed cryogenic neutron detector comprising an InSb semiconductor detector and a helium-3 gas converter. The neutron detector was operated at 4.2 K with helium-3 gas filling up to 1.5 atm, at which the density of the helium-3 nucleus corresponds to that at 160 atm at room temperature. The secondary particles generated by the $$^{3}$$He(n,p) T reaction were successfully detected by the InSb detector with a time response of $$sim$$80 nsec at all tested gas pressures.

JAEA Reports

An Investigation of methods for neutron dose measurement in high temperature irradiation fields

Kosako, Toshiso*; Sugiura, Nobuyuki*; Kudo, Kazuhiko*; Mori, Chizuo*; Iimoto, Takeshi*; Shikama, Tatsuo*; Katagiri, Masaki; Hayashi, Kimio; Aihara, Jun; Shibata, Taiju; et al.

JAERI-Review 2000-017, 78 Pages, 2000/10

JAERI-Review-2000-017.pdf:4.62MB

no abstracts in English

JAEA Reports

Compilation and review of information on nuclear disasters in Urals and their health effects

Sugiura, Nobuyuki; Hirano, Masashi

JAERI-M 92-010, 26 Pages, 1992/02

JAERI-M-92-010.pdf:0.96MB

no abstracts in English

32 (Records 1-20 displayed on this page)