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Journal Articles

Improving nuclear data accuracy of $$^{241}$$ Am and $$^{237}$$ Np capture cross sections

$v{Z}$erovnik, G.*; Schillebeeckx, P.*; Cano-Ott, D.*; Jandel, M.*; Hori, Junichi*; Kimura, Atsushi; Rossbach, M.*; Letourneau, A.*; Noguere, G.*; Leconte, P.*; et al.

EPJ Web of Conferences, 146, p.11035_1 - 11035_4, 2017/09

 Times Cited Count:3 Percentile:86.09(Nuclear Science & Technology)

Journal Articles

Preparation of microvolume anion-exchange cartridge for inductively coupled plasma mass spectrometry-based determination of $$^{237}$$Np content in spent nuclear fuel

Asai, Shiho; Hanzawa, Yukiko; Konda, Miki; Suzuki, Daisuke; Magara, Masaaki; Kimura, Takaumi; Ishihara, Ryo*; Saito, Kyoichi*; Yamada, Shinsuke*; Hirota, Hideyuki*

Analytical Chemistry, 88(6), p.3149 - 3155, 2016/03

 Times Cited Count:8 Percentile:29.59(Chemistry, Analytical)

Neptunium-237 ($$^{237}$$Np) is one of the major long-lived radionuclides found in spent nuclear fuel. To evaluate the long-term safety of a HLW repository, the $$^{237}$$Np content in spent nuclear fuel must be determined. In this study, micro-volume anion-exchange porous polymer disk-packed cartridges were prepared for Am-Np separation, which is required prior to the measurement of $$^{237}$$ Np with ICP-MS. Disks with a volume of 0.08 cm$$^{3}$$ were cut out from porous sheets having triethylenediamine (TEDA)-containing polymer chains densely attached on the pore surface. The resulting TEDA-introduced disk cartridge was applied to a spent nuclear fuel sample. The chemical yield of Np was 90.4%, which is sufficiently high for ICP-MS measurement of $$^{237}$$Np. Compared with the conventional separation technique using commercially available anion-exchange resin columns, the time required to adsorb, wash and elute Np using the TEDA-introduced disk cartridge was reduced by 75%.

Journal Articles

Revaluation of the correlation of isomer shift with Np-O bond length in various neptunyl(V and VI) compounds

Saeki, Masakatsu; Nakada, Masami; Kawasaki, Takeshi*; Nishimura, Tatsuru*; Kitazawa, Takafumi*; Takeda, Masuo*

Journal of Radioanalytical and Nuclear Chemistry, 270(2), p.379 - 384, 2006/11

 Times Cited Count:3 Percentile:24.08(Chemistry, Analytical)

no abstracts in English

JAEA Reports

Radiochemical studies of iodine, tritium and neptunium

Saeki, Masakatsu

JAERI-Review 2004-011, 54 Pages, 2004/03

JAERI-Review-2004-011.pdf:5.21MB

In this review, experimental results on studies of radioactive iodine, tritium and neptunium are summarized. On studies of radioactive iodine, from various experimental results, the process establishing the formation mechanism of organic iodides was fully described. On the basis of formation mechanism, possibilities for the formation of organic iodides under nuclear reactor accidents and so on were also discussed. On studies of tritium, three topics were concisely described on the isotopic composition of tritium gases, the chemical forms and the diffusivity of tritium in various materials, and the sorption and desorption behaviors of tritium on surfaces of various materials. On the neptunium chemistry, the relationship between the structure of neptunium compound and the Moessbauer isomer shift and experimental results on neptunyl(VI) hydroxides were discussed.

Journal Articles

Field tests on migration of TRU-nuclide, 3; Migration test of radionuclide in aerated soil layer

Mukai, Masayuki; Tanaka, Tadao; Maeda, Toshikatsu; Ogawa, Hiromichi; Matsumoto, Junko; Munakata, Masahiro; Zhao, Y.*; Guo, Z.*; Ni, S.*; Li, S.*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(3), p.342 - 349, 2003/09

Evaluation of radionuclide migration in geologic media is of great importance in safety assessment for shallow land disposal specially for TRU nuclides because of inadequate data based on field test. As a cooperative research between JAERI and CIRP, a field test of radionuclide migration was conducted under natural condition using Sr-90, Np-237 and Pu-238 to obtain migration data of the radionuclides in actual aerated layer under natural rainfall condition. Values of input parameters to an existing evaluation equation of nuclide migration were determined on the basis of the results of laboratory experiments of batch and column methods and field investigation. Migration distribution of the radionuclides calculated with the determined values showed reasonable agreement with the measured distribution of the field test. This confirmed an applicability of the evaluation equation for radionuclide migration to actual aerated layer under natural condition.

JAEA Reports

Adsorption mechanisms and models of $$^{85}$$Sr, $$^{237}$$Np, $$^{238}$$Pu and $$^{241}$$Am in loess media (Joint research)

Tanaka, Tadao; Mukai, Masayuki; Maeda, Toshikatsu; Matsumoto, Junko; Ogawa, Hiromichi; Li, S.*; Wang, Z.*; Wang, J.*; Guo, Z.*; Zhao, Y.*

JAERI-Research 2002-034, 20 Pages, 2002/12

JAERI-Research-2002-034.pdf:1.1MB

Adsorption mechanisms and models of $$^{85}$$Sr(II), $$^{237}$$Np(V), $$^{238}$$Pu(IV) and $$^{241}$$Am(III) on the loess were investigated from their adsorption and desorption properties. The distribution coefficient of $$^{85}$$Sr and $$^{237}$$Np was 2 - 3 orders of magnitude smaller than that of $$^{238}$$Pu and $$^{241}$$Am. The adsorption of $$^{85}$$Sr and $$^{237}$$Np was mainly controlled by the ion exchange reaction. On the other hand, the adsorption of $$^{238}$$Pu and $$^{241}$$Am was mostly controlled by the selective chemical reactions with Fe and Mn oxyhydroxide/oxide and humic substances. On the basis of the experimental results, several types of adsorption models of the radionuclides, considering elemental concentrations, adsorption mechanisms and kinetics, were proposed for setting up the analytical systems of radionuclide migration in the loess media.

Journal Articles

Spent fuel test of an advanced PUREX process:PARC

Mineo, Hideaki; Uchiyama, Gunzo; Hotoku, Shinobu; Asakura, Toshihide; Kihara, Takehiro; *; ; Kimura, Shigeru; *; ; et al.

Proc. of Int. Conf. on Future Nuclear Systems (GLOBAL'99)(CD-ROM), 7 Pages, 1999/00

no abstracts in English

Journal Articles

Recent measurements of fission neutron yield data of minor actinides

Oigawa, Hiroyuki; Shinohara, Nobuo; Mukaiyama, Takehiko; H.H.Saleh*; T.A.Parish*; W.H.Miller*; S.Raman*

Proc. of 4th Int. Information Exchange Meeting on Actinide and Fission Product Partitioning and Transm, 0, p.341 - 346, 1997/00

no abstracts in English

Journal Articles

Measurements of the number of neutrons emitted per fission in a fast neutron spectrum for $$^{235}$$U,$$^{237}$$Np, and $$^{243}$$Am

H.H.Saleh*; T.A.Parish*; W.H.Miller*; Oigawa, Hiroyuki; S.Raman*

Nuclear Instruments and Methods in Physics Research B, 103, p.393 - 400, 1995/00

 Times Cited Count:2 Percentile:32.08(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Inherent isotope dilution analysis of $$^{2}$$$$^{3}$$$$^{7}$$Np in spent nuclear fuels

; K.Kammerichs*; L.Koch*

Journal of Radioanalytical and Nuclear Chemistry, Letters, 117(4), p.233 - 241, 1987/04

no abstracts in English

Oral presentation

Accuracy improvement of thermal-neutron capture cross-section for Np-237

Nakamura, Shoji; Terada, Kazushi; Kimura, Atsushi; Nakao, Taro; Iwamoto, Osamu; Harada, Hideo; Uehara, Akihiro*; Fujii, Toshiyuki*

no journal, , 

As a part of the AIMAC Project, our group have measured the cross sections for Minor Actinides by an activation method with research reactors. In this presentation, we will clear up the cause of discrepancies among reported data for Np-237 in terms of the $$gamma$$-ray emission probability, experimental method and so on.

Oral presentation

Experimental verification of neutron capture cross section of $$^{237}$$Np in variable neutron field at KURRI-LINAC

Takahashi, Yoshiyuki*; Hori, Junichi*; Sano, Tadafumi*; Yashima, Hiroshi*; Nakamura, Shoji; Harada, Hideo

no journal, , 

Oral presentation

R&D for accuracy improvement of neutron nuclear data on minor actinides, 6; Measurements of neutron capture and total cross sections of $$^{237}$$Np by TOF method at KURRI-LINAC

Hori, Junichi*; Yashima, Hiroshi*; Sano, Tadafumi*; Takahashi, Yoshiyuki*; Harada, Hideo

no journal, , 

Neutron capture and total cross sections of $$^{237}$$Np have been measured by utilizing neutron time-of-flight method at KURRI-LINAC facility under the frame work of the research project "R&D for accuracy improvement of neutron nuclear data on minor actinides". Obtained results are compared with reported measurement values and evaluated data.

Oral presentation

Analysis of neutron-production double-differential cross sections in nuclear data measurements using the Kyoto University FFAG accelerator and measurement of a spallation neutron field using a $$^{237}$$Np fission chamber

Iwamoto, Hiroki; Meigo, Shinichiro; Satoh, Daiki; Iwamoto, Yosuke; Sugihara, Kenta*; Ishi, Yoshihiro*; Uesugi, Tomonori*; Kuriyama, Yasutoshi*; Yashima, Hiroshi*; Nishio, Katsuhisa; et al.

no journal, , 

no abstracts in English

14 (Records 1-14 displayed on this page)
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