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Journal Articles

Demonstration of a neutron resonance transmission analysis system using a laser-driven neutron source

Hironaka, Kota; Ito, Fumiaki*; Lee, J.; Koizumi, Mitsuo; Takahashi, Toon; Suzuki, Satoshi*; Yogo, Akifumi*; Arikawa, Yasunobu*; Abe, Yuki*

Dai-42-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 4 Pages, 2021/11

Neutron resonance transmission analysis (NRTA) is a method for non-destructive measurement of nuclear material by using a time-of-flight (TOF) technique with a pulsed neutron source. For NRTA system to carry out the short-distance TOF measurements with high resolutions, a short-pulsed neutron source is required. Laser-driven neutron sources (LDNSs) is very suitable as such a neutron source because of its short pulse width. Moreover, the compactness of the laser system is also expected due to the remarkable development of laser technology in recent years. In the present study, we have developed a technology for applying LDNS to the NRTA system and conducted the demonstration experiment using the LFEX laser at Osaka University to investigate the feasibility of the system. In this experiment, we successfully observed the neutron resonance peaks of indium and silver samples.

Journal Articles

Superdeformation in $$^{35}$$S

Go, Shintaro*; Ideguchi, Eiji*; Yokoyama, Rin*; Kobayashi, Motoki*; Kisamori, Keiichi*; Takaki, Motonobu*; Miya, Hiroyuki*; Ota, Shinsuke*; Michimasa, Shinichiro*; Shimoura, Susumu*; et al.

JPS Conference Proceedings (Internet), 6, p.030005_1 - 030005_4, 2015/06

JAEA Reports

Dissolutions of oxide dispersion strengthened ferritic steels in various nitric acid solutions, 2; The Amount of the corrosion products in the dissolution process

Inoue, Masaki; Suto, Mitsuo; Koyama, Shinichi; Otsuka, Satoshi; Kaito, Takeji

JAEA-Research 2013-009, 78 Pages, 2013/10

JAEA-Research-2013-009.pdf:3.75MB

In order to exammine the applicability for advanced aqueous reprocessing system, the martensitic oxide dispersion strengthened ferritic steel (9Cr-ODS steel), which is the primary candidate material for high burnup fuel pin cladding tube in fast reactor cycle, was evaluated for the amount of corrosion products in the dissolution process. The quantity of corrosion products was calculated to investigate the influence of both various chemical processes and waste glass (vitrified high level radioactive wastes) by use of the results of a maximum cladding temperature fuel subassembly and the sum of all fuel subassemblies, respectively. The experimental results of immersion tests in flowing liquid sodium loops and fuel pin irradiation tests in fast reactors were reviewed to consider the effect of outer and inner corrosions in high burnup fuel pins on corrosion products. This work revealed that the sum of corrosion products depends largely on the mass transfer behavior in flowing liquid sodium.

Journal Articles

Application of glutathione to roots selectively inhibits cadmium transport from roots to shoots in oilseed rape

Nakamura, Shinichi*; Suzui, Nobuo; Nagasaka, Toshinori*; Komatsu, Fumiya*; Ishioka, Noriko; Ito, Sayuri*; Kawachi, Naoki; Rai, Hiroki*; Hattori, Hiroyuki*; Chino, Mitsuo*; et al.

Journal of Experimental Botany, 64(4), p.1073 - 1081, 2013/02

 Times Cited Count:47 Percentile:87.93(Plant Sciences)

JAEA Reports

A Study on the technology for reducing cement-type materials used for tunnel supports at high-level radioactive waste disposal sites (Joint research)

Hayashi, Katsuhiko; Noguchi, Akira; Kishi, Hirokazu; Kabayashi, Yasushi*; Nakama, Shigeo; Fujita, Tomo; Naito, Morimasa; Tada, Hiroyuki*; Kumasaka, Hiroo*; Goke, Mitsuo*; et al.

JAEA-Research 2010-057, 101 Pages, 2011/03

JAEA-Research-2010-057.pdf:7.47MB

Cement-type materials that are used for supports or grouting at high-level radioactive waste disposal facilities leach into the groundwater and create a highly alkaline environment. Of concern in highly alkaline environments are the alteration of bentonite used as buffers or backfill materials, and of surrounding rock mass, and the increased uncertainty regarding the provision of performance of the disposal system over a long period of time. In this study, to reduce the quantity of cement-type materials that cause highly alkaline environments, technical feasibility of the support structure including the materials which considered the long-term performance of the HLW disposal system are discussed by using knowledge and technology accumulated in JAEA and Shimizu Construction. Moreover, based on the results, the problems remained in the application to the future HLW disposal institution are summarized.

Journal Articles

Visualization of $$^{107}$$Cd accumulation in oilseed rape plants treated with glutathione

Nakamura, Shinichi*; Suzui, Nobuo; Ito, Sayuri*; Kawachi, Naoki; Ishioka, Noriko; Rai, Hiroki*; Hattori, Hiroyuki*; Chino, Mitsuo*; Fujimaki, Shu

JAEA-Review 2010-065, JAEA Takasaki Annual Report 2009, P. 104, 2011/01

Journal Articles

In situ and time-resolved small-angle neutron scattering observation of star polymer formation via arm-linking reaction in ruthenium-catalyzed living radical polymerization

Terashima, Takaya*; Motokawa, Ryuhei; Koizumi, Satoshi*; Sawamoto, Mitsuo*; Kamigaito, Masami*; Ando, Tsuyoshi*; Hashimoto, Takeji*

Macromolecules, 43(19), p.8218 - 8232, 2010/10

 Times Cited Count:37 Percentile:77.54(Polymer Science)

Journal Articles

Local and electronic structure of Am$$_{2}$$O$$_{3}$$ and AmO$$_{2}$$ with XAFS spectroscopy

Nishi, Tsuyoshi; Nakada, Masami; Suzuki, Chikashi; Shibata, Hiroki; Ito, Akinori; Akabori, Mitsuo; Hirata, Masaru

Journal of Nuclear Materials, 401(1-3), p.138 - 142, 2010/06

 Times Cited Count:25 Percentile:87.19(Materials Science, Multidisciplinary)

XAFS studies were performed in a study of americium sesquioxide (Am$$_{2}$$O$$_{3}$$) with A-type rare earth oxide structure and americium dioxide (AmO$$_{2}$$) with fluorite structure. EXAFS results for Am-L$$_{3}$$ absorption edge of Am$$_{2}$$O$$_{3}$$ and AmO$$_{2}$$ were good agreement with the crystallographic data from X-ray diffraction analysis. In order to characterize XANES in aspect of the electronic states, the theoretical assignments for the Am$$_{2}$$O$$_{3}$$ and AmO$$_{2}$$ were performed with the all-electron full potential linearized augmented plane wave (FP-LAPW) method. The theoretical XANES spectra of Am$$_{2}$$O$$_{3}$$ and AmO$$_{2}$$ well reproduced the experimental ones. In addition, it was found that the white line peak was created due to the interaction between Am-d and O-p components, and the broad peak and the tail peak were created due to the interaction between Am-d and O-d component.

Journal Articles

Thermalconductivities of (Np,Am)N and (Pu,Am)N solid solutions

Nishi, Tsuyoshi; Takano, Masahide; Ito, Akinori; Miyata, Seiichi; Akabori, Mitsuo; Arai, Yasuo; Minato, Kazuo

IOP Conference Series; Materials Science and Engineering, 9, p.012017_1 - 012017_8, 2010/05

 Times Cited Count:2 Percentile:73.44

The thermal diffusivities and heat capacities of transuranium nitride solid solutions, (Np,Am)N and (Pu,Am)N, were measured by using a laser flash method and a drop calorimetry, respectively. The thermal conductivities of these samples were determined from the measured thermal diffusivities, heat capacities and bulk densities. The thermal conductivities of (Np,Am)N and (Pu,Am)N increased with temperature over the temperature range investigated. The increases in the thermal conductivities were probably due to the increase of electrical components. In addition, the thermal conductivities of (Np,Am)N and (Pu,Am)N decreased with increasing Am contents. It could be considered that the decreases in the thermal conductivities correspond to the lowering of electronic contribution.

Journal Articles

Recent progress in the energy recovery linac project in Japan

Sakanaka, Shogo*; Akemoto, Mitsuo*; Aoto, Tomohiro*; Arakawa, Dai*; Asaoka, Seiji*; Enomoto, Atsushi*; Fukuda, Shigeki*; Furukawa, Kazuro*; Furuya, Takaaki*; Haga, Kaiichi*; et al.

Proceedings of 1st International Particle Accelerator Conference (IPAC '10) (Internet), p.2338 - 2340, 2010/05

Future synchrotron light source using a 5-GeV energy recovery linac (ERL) is under proposal by our Japanese collaboration team, and we are conducting R&D efforts for that. We are developing high-brightness DC photocathode guns, two types of cryomodules for both injector and main superconducting (SC) linacs, and 1.3 GHz high CW-power RF sources. We are also constructing the Compact ERL (cERL) for demonstrating the recirculation of low-emittance, high-current beams using above-mentioned critical technologies.

Journal Articles

Tracing cadmium from culture to spikelet; Noninvasive imaging and quantitative characterization of absorption, transport, and accumulation of cadmium in an intact rice plant

Fujimaki, Shu; Suzui, Nobuo; Ishioka, Noriko; Kawachi, Naoki; Ito, Sayuri; Chino, Mitsuo*; Nakamura, Shinichi*

Plant Physiology, 152(4), p.1796 - 1806, 2010/02

 Times Cited Count:157 Percentile:98.03(Plant Sciences)

Journal Articles

Thermal conductivities of neptunium and americium mononitrides

Nishi, Tsuyoshi; Takano, Masahide; Ito, Akinori; Akabori, Mitsuo; Arai, Yasuo; Minato, Kazuo

Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 8 Pages, 2010/00

Neptunium nitride (NpN) and americium nitride (AmN) were prepared by carbothermic reduction of the respective dioxides. The thermal diffusivities of NpN and AmN were measured by using a laser flash method. The heat capacities of NpN and AmN were determined with the drop calorimetry. The thermal diffusivity of NpN tends to remain unchanged with increasing temperature in the temperature range from 473 to 1473 K, and that of AmN tends to slightly decrease with increasing temperature in the same temperature range. The heat capacity of NpN obtained was close to those of UN and PuN, while that of AmN was slightly smaller than those of UN, NpN and PuN. The thermal conductivities of NpN and AmN were determined from the measured thermal diffusivities, heat capacities and bulk densities. It was found that the thermal conductivities of NpN and AmN slightly increased with temperature in the temperature range investigated.

Journal Articles

Visualization of $$^{107}$$Cd translocation in Tobacco plants

Nakamura, Shinichi*; Suzui, Nobuo; Ishioka, Noriko; Kawachi, Naoki; Ito, Sayuri; Hattori, Hiroyuki*; Chino, Mitsuo*; Fujimaki, Shu

JAEA-Review 2009-041, JAEA Takasaki Annual Report 2008, P. 103, 2009/12

Journal Articles

Non-invasive imaging and characterization of absorption, transport and accumulation of cadmium in an intact rice plant

Fujimaki, Shu; Suzui, Nobuo; Ishioka, Noriko; Kawachi, Naoki; Ito, Sayuri; Chino, Mitsuo*; Nakamura, Shinichi*

Proceedings of 16th International Plant Nutrition Colloquium (IPNC-16) (Internet), 1 Pages, 2009/04

The absorption, transport and accumulation of cadmium (Cd) in rice were analyzed quantitatively using the positron-emitting tracer imaging system (PETIS). We developed a method to produce $$^{107}$$Cd tracer and obtained serial images of Cd distribution in intact rice plants at vegetative stage and grain-filling stage using PETIS. The results suggest that xylem-to-phloem transfer is a pivotal process on the route from the soil to the grains and the nodes are the most likely organ where the transfer takes place.

Journal Articles

Non-invasive imaging of cadmium distribution in intact oilseed rape plants

Nakamura, Shinichi*; Suzui, Nobuo; Ishioka, Noriko; Kawachi, Naoki; Ito, Sayuri; Rai, Hiroki*; Hattori, Hiroyuki*; Chino, Mitsuo*; Fujimaki, Shu

Proceedings of 16th International Plant Nutrition Colloquium (IPNC-16) (Internet), p.1181_1 - 1181_2, 2009/04

JAEA Reports

Analytical work at NUCEF in FY 2007

Abe, Hiroyoshi; Haga, Takahisa; Fukaya, Hiroyuki; Sonoda, Takashi; Sakazume, Yoshinori; Ito, Mitsuo; Shirahashi, Koichi

JAEA-Technology 2009-008, 24 Pages, 2009/03

JAEA-Technology-2009-008.pdf:5.62MB

Analysis of the uranyl nitrate solution fuel is carried out at the analytical laboratory of NUCEF (Nuclear Fuel Cycle Engineering Research Facility), which provides essential data for operation of STACY (Static Experiment Critical Facility), TRACY (Transient Experiment Critical Facility) and the fuel treatment system. Analyzed in FY 2007 were uranyl nitrate solution fuel samples taken before and after experiments of STACY and TRACY, samples for the preparation and pulification of uranyl nitrate solution fuel in the fuel treatment system and samples for nuclear material accountancy purpose. The total number of the samples analyzed in FY 2007 was 143. This report summarizes work related to the analysis and management of the analytical laboratory in the FY 2007.

JAEA Reports

Recent progress of analytical methods of spent nuclear fuel, Review

Yoshida, Zenko; Watanabe, Kazuo; Ito, Mitsuo; Ueno, Takashi; Takeshita, Hidefumi

JAEA-Review 2008-062, 34 Pages, 2009/01

JAEA-Review-2008-062.pdf:4.07MB

Analytical methods for the spent nuclear fuel (SF) have been greatly innovated recently. This methodological innovation is mainly caused by rapid and remarkable progress of induced coupled plasma-mass spectrometry (ICP-MS) which is utilized for the isotopic analysis of actinoid elements (U, Np, Pu, Am, Cm) and fission product elements in the SF samples. The quantity of the objective element as well as the volume of the sample solution needed for the ICP-MS measurement are, in principle, much less than those required for the measurement by other analytical methods. ICP-MS makes it possible to reduce the radiation dose of the operator and to minimize the amount of the radioactive wastes generated from the analytical work. For the precise and accurate isotopic analysis of the objective element in the SF sample by mass spectrometry, the interfering element having isobars needs to be separated prior to the measurement. This review highlights the development of the separation methods and isotopic analysis methods for the analysis of the SF based on more than 50 recent publications and the future problems to be solved and prospects are discussed.

Journal Articles

Heat capacities of NpN and AmN

Nishi, Tsuyoshi; Ito, Akinori; Takano, Masahide; Numata, Masami; Akabori, Mitsuo; Arai, Yasuo; Minato, Kazuo

Journal of Nuclear Materials, 377(3), p.467 - 469, 2008/07

 Times Cited Count:12 Percentile:65.48(Materials Science, Multidisciplinary)

The specific heat capacities of NpN and AmN were determined by the drop calorimetry method. The NpN and AmN samples were prepared by the carbothermic reduction of the respective dioxides. The specific heat capacity of NpN obtained was in good agreement with the reported values in the temperature range from 334 to 1067 K, which was close to those of UN and PuN. The specific heat capacity of AmN was obtained experimentally for the first time, which was slightly smaller than those of UN, NpN and PuN in the temperature range from 354 to 1071 K.

Journal Articles

Progress in R&D efforts on the energy recovery linac in Japan

Sakanaka, Shogo*; Ago, Tomonori*; Enomoto, Atsushi*; Fukuda, Shigeki*; Furukawa, Kazuro*; Furuya, Takaaki*; Haga, Kaiichi*; Harada, Kentaro*; Hiramatsu, Shigenori*; Honda, Toru*; et al.

Proceedings of 11th European Particle Accelerator Conference (EPAC '08) (CD-ROM), p.205 - 207, 2008/06

Future synchrotron light sources based on the energy-recovery linacs (ERLs) are expected to be capable of producing super-brilliant and/or ultra-short pulses of synchrotron radiation. Our Japanese collaboration team is making efforts for realizing an ERL-based hard X-ray source. We report recent progress in our R&D efforts.

Journal Articles

Thermal conductivity of neptunium dioxide

Nishi, Tsuyoshi; Ito, Akinori; Takano, Masahide; Numata, Masami; Akabori, Mitsuo; Arai, Yasuo; Minato, Kazuo

Journal of Nuclear Materials, 376(1), p.78 - 82, 2008/05

 Times Cited Count:31 Percentile:89.3(Materials Science, Multidisciplinary)

The thermal diffusivity of neptunium dioxide was measured in the temperature range from 473 to 1473 K by a laser flash method. The thermal diffusivity slightly decreased with increasing temperature in the temperature range investigated. The specific heat capacity of NpO$$_{2}$$ was measured in the temperature range from 334 to 1071 K by a drop calorimetry method. The specific heat capacity of NpO$$_{2}$$ determined in this study was slightly larger than that of UO$$_{2}$$ and about 7 % smaller than that of PuO$$_{2}$$. The thermal conductivity of NpO$$_{2}$$ was determined from the thermal diffusivity, the specific heat capacity and the bulk density. It was found that the thermal conductivity of NpO$$_{2}$$ from 873 to 1473 K existed between those of UO$$_{2}$$ and PuO$$_{2}$$.

129 (Records 1-20 displayed on this page)