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Journal Articles

Microscopic analyses on Zr adsorbed IDA chelating resin by PIXE and EXAFS

Arai, Yoichi; Watanabe, So; Ono, Shimpei; Nomura, Kazunori; Nakamura, Fumiya*; Arai, Tsuyoshi*; Seko, Noriaki*; Hoshina, Hiroyuki*; Hagura, Naoto*; Kubota, Toshio*

Nuclear Instruments and Methods in Physics Research B, 477, p.54 - 59, 2020/08

 Times Cited Count:0 Percentile:100(Instruments & Instrumentation)

Journal Articles

Quantitative analysis of Zr adsorbed on IDA chelating resin using Micro-PIXE

Arai, Yoichi; Watanabe, So; Ono, Shimpei; Nomura, Kazunori; Nakamura, Fumiya*; Arai, Tsuyoshi*; Seko, Noriaki*; Hoshina, Hiroyuki*; Kubota, Toshio*

QST-M-23; QST Takasaki Annual Report 2018, P. 59, 2020/03

Journal Articles

Improvement in flow-sheet of extraction chromatography for trivalent minor actinides recovery

Watanabe, So; Senzaki, Tatsuya; Shibata, Atsuhiro; Nomura, Kazunori; Takeuchi, Masayuki; Nakatani, Kiyoharu*; Matsuura, Haruaki*; Horiuchi, Yusuke*; Arai, Tsuyoshi*

Journal of Radioanalytical and Nuclear Chemistry, 322(3), p.1273 - 1277, 2019/12

 Times Cited Count:0 Percentile:100(Chemistry, Analytical)

Journal Articles

STRAD project for systematic treatments of radioactive liquid wastes generated in nuclear facilities

Watanabe, So; Ogi, Hiromichi*; Arai, Yoichi; Aihara, Haruka; Takahatake, Yoko; Shibata, Atsuhiro; Nomura, Kazunori; Kamiya, Yuichi*; Asanuma, Noriko*; Matsuura, Haruaki*; et al.

Progress in Nuclear Energy, 117, p.103090_1 - 103090_8, 2019/11

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

Journal Articles

Extraction mechanism of lanthanide ions into silica-based microparticles studied by single microparticle manipulation and microspectroscopy

Otaka, Toshiki*; Sato, Tatsumi*; Ono, Shimpei; Nagoshi, Kohei; Abe, Ryoji*; Arai, Tsuyoshi*; Watanabe, So; Sano, Yuichi; Takeuchi, Masayuki; Nakatani, Kiyoharu*

Analytical Sciences, 35(10), p.1129 - 1133, 2019/10

 Times Cited Count:0 Percentile:100(Chemistry, Analytical)

Journal Articles

Ion beam induced luminescence of complexes formed in adsorbent for MA recovery process

Watanabe, So; Katai, Yuya*; Matsuura, Haruaki*; Kada, Wataru*; Koka, Masashi*; Sato, Takahiro*; Arai, Tsuyoshi*

Nuclear Instruments and Methods in Physics Research B, 450, p.61 - 65, 2019/07

 Times Cited Count:1 Percentile:58.8(Instruments & Instrumentation)

Journal Articles

Influences of pore and particle sizes of CMPO/SiO$$_{2}$$-P adsorbent on extraction chromatography process

Watanabe, So; Sano, Yuichi; Sanda, Shuhei*; Sakurai, Shota*; Arai, Tsuyoshi*

Nippon Ion Kokan Gakkai-Shi, 30(1), p.8 - 16, 2019/01

Journal Articles

Microanalysis of silica-based adsorbent for effective recovery of radioactive elements

Sano, Yuichi; Watanabe, So; Matsuura, Haruaki*; Nagoshi, Kohei*; Arai, Tsuyoshi*

Journal of Nuclear Science and Technology, 54(10), p.1058 - 1064, 2017/10

 Times Cited Count:3 Percentile:50.46(Nuclear Science & Technology)

For effective recovery of radioactive elements by adsorbents using polymer-immobilized silica (SiO$$_{2}$$-P) supports, the microstructure of SiO$$_{2}$$-P particles impregnated with CMPO as extractants and their change with the crosslinking degree of polymer (CDP) were investigated using STXM and EXAFS analyses; further, their relation with adsorption/elution behavior was discussed. The adsorption/elution tests using adsorbents with a different CDP demonstrated that a higher CDP inhibited the elution of adsorbed metal ions from the adsorbent. The results of STXM and EXAFS analyses suggested that adsorption by CMPO proceeds through the entire area in the adsorbent and the local structure around adsorbed metal ions is similar irrespective of the CDP. Conversely, STXM analyses implied the capture of eluents such as H$$_{2}$$O by polymers with high CDP, which suppresses the prompt elution of adsorbed metal ions from the adsorbent.

Journal Articles

Local structure and distribution of remaining elements inside extraction chromatography adsorbents

Watanabe, So; Sano, Yuichi; Shiwaku, Hideaki; Yaita, Tsuyoshi; Ono, Shimpei*; Arai, Tsuyoshi*; Matsuura, Haruaki*; Koka, Masashi*; Sato, Takahiro*

Nuclear Instruments and Methods in Physics Research B, 404, p.202 - 206, 2017/08

 Times Cited Count:3 Percentile:50.46(Instruments & Instrumentation)

Journal Articles

Microscopic analyses of complexes formed in adsorbent for Mo and Zr separation chromatography

Abe, Ryoji*; Nagoshi, Kohei*; Arai, Tsuyoshi*; Watanabe, So; Sano, Yuichi; Matsuura, Haruaki*; Takagi, Hideaki*; Shimizu, Nobutaka*; Koka, Masashi*; Sato, Takahiro*

Nuclear Instruments and Methods in Physics Research B, 404, p.173 - 178, 2017/08

 Times Cited Count:1 Percentile:80.48(Instruments & Instrumentation)

Journal Articles

Effect of surface treatment on adsorption and desorption behavior of impregnated adsorbent for extraction chromatography

Nagoshi, Kohei*; Arai, Tsuyoshi*; Watanabe, So; Sano, Yuichi; Takeuchi, Masayuki; Sato, Mutsumi*; Oikawa, Hiroshi*

Nippon Ion Kokan Gakkai-Shi, 28(1), p.11 - 18, 2017/01

no abstracts in English

Journal Articles

Uranyl species in 1-Ethyl-3-methylimidazolium nitrate ([EMI][NO$$_{3}$$]) solution of [EMI]$$_{2}$$[UO$$_{2}$$(NO$$_{3}$$)$$_{4}$$]; First spectrophotometric evidence for existence of [UO$$_{2}$$(NO$$_{3}$$)$$_{4}$$]$$^{2-}$$

Sasaki, kotoe*; Suzuki, Tomoya*; Arai, Tsuyoshi*; Takao, Koichiro*; Suzuki, Shinichi; Yaita, Tsuyoshi; Ikeda, Yasuhisa*

Chemistry Letters, 43(5), p.670 - 672, 2014/05

 Times Cited Count:5 Percentile:74.63(Chemistry, Multidisciplinary)

no abstracts in English

JAEA Reports

Property database of TRU nitride fuel

Nishi, Tsuyoshi; Arai, Yasuo; Takano, Masahide; Kurata, Masaki

JAEA-Data/Code 2014-001, 45 Pages, 2014/03

JAEA-Data-Code-2014-001.pdf:3.57MB
JAEA-Data-Code-2014-001(errata).pdf:0.2MB

The purpose of this study is to prepare a property database of nitride fuel needed for the fuel design of accelerator-driven system (ADS) for transmutation of minor actinide (MA). Nitride fuel of ADS is characterized by high content of Pu and MA as principal components, and addition of a diluent material such as ZrN. Experimental data or evaluated values from the raw data on properties Pu and MA nitrides, and nitride solid solutions containing ZrN are collected and summarized, which cover the properties needed for the fuel design of ADS. They are expressed as an equation as much as possible for corresponding to a variety conditions. Error evaluation is also made as much as possible. Since property data on transuranium (TRU) nitrides are often lacking, those on UN and (U,Pu)N are substitutionally shown in such cases in order to facilitate the fuel design with a tolerable accuracy by complementing the database.

Journal Articles

Thermal conductivity of minor actinide nitride fuels

Nishi, Tsuyoshi; Takano, Masahide; Arai, Yasuo; Kurata, Masaki

Dai-34-Kai Nippon Netsu Bussei Shimpojiumu Koen Rombunshu, p.199 - 201, 2013/11

By installing the laser flash apparatus and the drop calorimeter in the glove box, the thermal diffusivity and the heat capacity measurements of nitride containing MA elements of long-lived radioactive nuclides were enabled. The sample holder and the platinum container were designed to measure the thermal diffusivity and the heat capacity of very small quantity of MA nitride samples. The thermal conductivities of MA nitride increased with temperature, unlike that of conventional oxide-type nuclear fuels. In addition, the thermal conductivities of MA nitride decreased with increasing Am contents. The thermal conductivity of ZrN-based MA nitride, which is proposed as a candidate material for the ADS fuel, was fitted to equations as functions of the temperature and ZrN concentration. The predicted values agreed well with the experimental ones, indicating that the thermal conductivity of nitride fuel for ADS can be predicted for a practical design.

Journal Articles

Thermal conductivity of (Np$$_{0.20}$$Pu$$_{0.50}$$Am$$_{0.25}$$Cm$$_{0.05}$$)O$$_{2-x}$$ solid solutions

Nishi, Tsuyoshi; Takano, Masahide; Akabori, Mitsuo; Arai, Yasuo

Journal of Nuclear Materials, 440(1-3), p.534 - 538, 2013/09

 Times Cited Count:2 Percentile:77.33(Materials Science, Multidisciplinary)

To clarify the dependence of thermal conductivity on storage time of curium containing oxide, the authors prepared the sintered sample of (Np$$_{0.20}$$Pu$$_{0.50}$$Am$$_{0.25}$$Cm$$_{0.05}$$)O$$_{2-x}$$ (x = 0.02, 0.04) solid solutions and evaluated the thermal conductivity. The thermal conductivities of (Np$$_{0.20}$$Pu$$_{0.50}$$Am$$_{0.25}$$Cm$$_{0.05}$$)O$$_{2-x}$$ exponentially decreased with increasing storage duration. This result suggested that the degradation of the thermal conductivities was attributed to the accumulation of lattice defects by self-irradiation.

Journal Articles

Self-irradiation effect on thermal conductivity of (Pu$$_{0.91}$$Cm$$_{0.09}$$)O$$_{2}$$

Nishi, Tsuyoshi; Takano, Masahide; Akabori, Mitsuo; Arai, Yasuo

Journal of Nuclear Materials, 433(1-3), p.531 - 533, 2013/02

 Times Cited Count:5 Percentile:53.31(Materials Science, Multidisciplinary)

To clarify the storage duration dependence of the thermal conductivity of MA containing oxide fuel, the thermal diffusivity of (Pu$$_{0.91}$$Cm$$_{0.09}$$)O$$_{2}$$ was measured at 473, 523 and 573 K by a laser flash method using the sample stored for 48, 264, 504, and 960 h. The heat capacity was measured by a drop calorimetry to derive the thermal conductivity. It was confirmed that the degradation of the thermal conductivity was attributed to the accumulation of lattice defects caused by self-irradiation, because the storage duration dependence of the thermal conductivity could be approximated by the equation used for self-irradiation lattice expansion model.

Journal Articles

Optimizing composition of TODGA/SiO$$_{2}$$-P adsorbent for extraction chromatography process

Watanabe, So; Arai, Tsuyoshi*; Ogawa, Tsuyoshi*; Takizawa, Makoto*; Sano, Kyohei*; Nomura, Kazunori; Koma, Yoshikazu

Procedia Chemistry, 7, p.411 - 417, 2012/00

 Times Cited Count:9 Percentile:4.73

Journal Articles

Fabrication of U-Pu-Zr metallic fuel elements for the irradiation test at experimental fast test reactor Joyo

Nakamura, Kinya*; Ogata, Takanari*; Kikuchi, Hironobu; Iwai, Takashi; Nakajima, Kunihisa; Kato, Tetsuya*; Arai, Yasuo; Uozumi, Koichi*; Hijikata, Takatoshi*; Koyama, Tadafumi*; et al.

Nippon Genshiryoku Gakkai Wabun Rombunshi, 10(4), p.245 - 256, 2011/12

Sodium-bonded metallic fuel elements were fabricated for the first time in Japan for the irradiation test in the experimental fast test reactor JOYO. U-20Pu-10Zr fuel slugs of 200 mm in length and approximately 5 mm in diameter were fabricated in a small-scale injection casting furnace. Each fuel slug was loaded into the ferritic martenstic stainless steel (PNC-FMS) cladding tube with the sodium thermal bond, thermal insulator and reflector in a helium gas atmosphere glove box. After top-end plug welding to the cladding tube and heat treatment of the welding area, each fuel element was subjected to the sodium bonding process. After the inspection such as element length, gas plenum length and helium-leak tightness, six metallic fuel elements are transported to the JOYO site for the coming irradiation test.

Journal Articles

Thermal conductivities of (Zr$$_{x}$$Pu$$_{(1-x)/2}$$Am$$_{(1-x)/2}$$)N solid solutions

Nishi, Tsuyoshi; Takano, Masahide; Akabori, Mitsuo; Arai, Yasuo

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 6 Pages, 2011/12

The thermal conductivity of Zr-based minor actinide (MA) nitride solid solutions is important for designing subcritical cores in nitride-fueled ADS. However, there have been no experimental data on the thermal conductivities of Zr-based nitride solid solutions containing MA. In this study, the authors prepared sintered samples of (Zr$$_{x}$$Pu$$_{(1-x)/2}$$Am$$_{(1-x)/2}$$)N (x=0.0, 0.58, 0.80) solid solutions. The thermal diffusivity and heat capacity of (Zr$$_{x}$$Pu$$_{(1-x)/2}$$Am$$_{(1-x)/2}$$)N solid solutions were measured using a laser flash method and drop calorimetry, respectively. Thermal conductivities were determined from the measured thermal diffusivities, heat capacities and bulk densities over a temperature range of 473 to 1473 K. Moreover, in order to help to promote the design study of nitride-fueled ADS, the thermal conductivity of the (Zr$$_{x}$$Pu$$_{(1-x)/2}$$Am$$_{(1-x)/2}$$)N solid solutions were fitted to an equation using the least squares method.

Journal Articles

Analysis of contact length distribution of superconducting strands with copper sleeves at cable-in-conduit conductor joints

Nakazawa, Shinobu*; Teshima, Shotaro*; Arai, Daichi*; Miyagi, Daisuke*; Tsuda, Makoto*; Hamajima, Takataro*; Yagai, Tsuyoshi*; Nunoya, Yoshihiko; Koizumi, Norikiyo; Takahata, Kazuya*; et al.

Teion Kogaku, 46(8), p.474 - 480, 2011/08

It is observed that measured critical currents of a large current CIC conductor sample become lower than expected ones, since unbalanced current distribution is caused through contacting resistances between strands and Cu sleeves in CIC conductor joints. In order to evaluate the contacting length, we identify all strands 3 dimensional positions in the CIC conductor, and then we measure contacting number and lengths of strands which appear on surface of the cable for contacting with the Cu sleeves. It is found that some strands do not appear on the surface of cable and the contacting lengths are widely distributed with large standard deviation. We develop a numerical code which simulates strand positions in the CIC, and then compare the analyzed contacting strand number and contacting length with measured ones. It is found that the both results are in good agreement and hence the code is available for evaluating the contacting parameters. We vary twist pitches of sub-cables to search the contacting parameters and then show that all strands appear on the cable surface and have contacting lengths with small standard deviation. It is found that the twist pitches are a key parameter for optimization of the contacting parameters.

144 (Records 1-20 displayed on this page)