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Journal Articles

Solvent extraction of technetium(VII) and rhenium(VII) using a hexaoctylnitrilotriacetamide extractant

Shimojo, Kojiro; Suzuki, Hideya; Yokoyama, Keiichi; Yaita, Tsuyoshi; Ikeda, Atsushi

Analytical Sciences, 36(12), p.1435 - 1437, 2020/12

 Times Cited Count:14 Percentile:63.71(Chemistry, Analytical)

Liquid-liquid extraction for the removal of pertechnetate ($$^{99}$$TcO$$_{4}$$$$^{-}$$) and perrhenate (ReO$$_{4}$$$$^{-}$$) is reported using tripodal extractant $$N,N,N',N',N'',N''$$-hexa-$$n$$-octylnitrilotriacetamide (HONTA) composed of three amide groups and a tertiary amine. The extraction behavior was compared with those using alkyldiamideamines (ADAAM(Oct) and ADAAM(EH)), and the commercial amine-type extractant, trioctylamine (TOA). HONTA quantitatively extracted $$^{99}$$TcO$$_{4}$$$$^{-}$$ and ReO$$_{4}$$$$^{-}$$ in the pH range from 1.0 to 2.5 by co-extraction of protons. Extraction performance of extractants was improved in the order of HONTA $$>$$ ADAAM(Oct) $$>$$ ADAAM(EH) $$>$$ TOA. $$^{99}$$TcO$$_{4}$$$$^{-}$$ and ReO$$_{4}$$$$^{-}$$ in the extracting phase were successfully stripped using neutral aqueous solutions as the receiving phase, and the extraction ability of HONTA was maintained after five repeated uses.

JAEA Reports

JENDL Dosimetry File 99 (JENDL/D-99)

Kobayashi, Katsuhei*; Iguchi, Tetsuo*; Iwasaki, Shin*; Aoyama, Takafumi*; Shimakawa, Satoshi; Ikeda, Yujiro; Odano, Naoteru; Sakurai, Kiyoshi; Shibata, Keiichi; Nakagawa, Tsuneo; et al.

JAERI 1344, 133 Pages, 2002/01

JAERI-1344.pdf:7.59MB

The JENDL Dosimetry File 99 (JENDL/D-99) has been prepared for determinations of neutron flux/fluence and energy spectrum at specific neutron fields. This file contains data for 67 reactions with 47 nuclides. Cross sections for 33 major dosimetry reactions and their covariance data were simultaneously generated and the other 34 reaction data were mainly adopted from the first version, JENDL/D-91. The GMA code was mainly used for most of the evaluation procedures by referring the basic experimental data in EXFOR. The resultant data are given in the neutron energy region below 20 MeV in both of point-wise and group-wise files in the ENDF-6 format. In order to confirm reliability of the data, several integral tests have been carried out: comparison with the data in IRDF-90V2 and average cross sections measured in fission neutron fields, fast/thermal reactor spectra, DT neutron fields and Li(d,n) neutron fields. The contents of JENDL/D-99 and the results of the integral tests are described in this report. All of the dosimetry cross sections are shown in a graphical form in the Appendix.

JAEA Reports

Study on Evaluation of Internal Exposure Dose

Miyahara, H.*; Narita, N.*; Ikeda, Keiichi*; Kato, Y.*; Fujiki, K.*; Momose, Takumaro; Tasaki, Takashi; Kurihara, Osamu; Hayashi, Naomi

JNC TY8400 2001-002, 81 Pages, 2001/07

JNC-TY8400-2001-002.pdf:2.35MB

no abstracts in English

Journal Articles

JENDL PKA/KERMA file for IFMIF project

Fukahori, Tokio; Chiba, Satoshi; Shibata, Keiichi; Ikeda, Yujiro; Aruga, Takeo; Watanabe, Yukinobu*; Murata, Toru*; Yamano, Naoki*; Kawai, Masayoshi*

Reactor Dosimetry: Radiation Metrology and Assessment (ASTM STP 1398), p.591 - 598, 2001/00

no abstracts in English

Journal Articles

Measurement and evaluation of nuclear data

Takahashi, Akito*; Shibata, Keiichi; Ikeda, Yujiro

Purazuma, Kaku Yugo Gakkai-Shi, 71(11), p.1113 - 1122, 1995/11

no abstracts in English

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