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Journal Articles

Measurements of neutron capture cross section of $$^{237}$$Np for fast neutrons

Harada, Hideo; Nakamura, Shoji; Hatsukawa, Yuichi; Toh, Yosuke; Kimura, Atsushi; Ishiwatari, Yuki*; Yasumi, Atsushi*; Mabuchi, Yukio*; Nakagawa, Tsutomu*; Okamura, Kazuo*; et al.

Journal of Nuclear Science and Technology, 46(5), p.460 - 468, 2009/05

 Times Cited Count:4 Percentile:30.43(Nuclear Science & Technology)

The neutron capture cross section of $$^{237}$$Np has been measured for fast neutrons supplied at the center of the core in the Yayoi reactor. The activation method was used for the measurement, in which the amount of the product $$^{238}$$Np was determined by $$gamma$$-ray spectroscopy using a Ge detector. The representative neutron energy and the corresponding capture cross section of $$^{237}$$Np in the experiment were analytically deduced as 0.80 $$pm$$ 0.04 b at 0.214 $$pm$$ 0.009 MeV from the measured reaction rate by combining the energy dependence of the cross section in the nuclear data library ENDF/VII.0. The deduced cross section of $$^{237}$$Np at the representative neutron energy agrees with the evaluated data of ENDF/B-VII.0, but shows 15% larger value than that of JENDL-3.3 and 13% larger value than that of JENDL/AC-2008.

Journal Articles

Applications of extraction chromatography in the bifunctional extractant-nitric acid system for separation of actinides in nuclear fuel cycle

Kimura, Takaumi; Akatsu, Jokun

Solvent Extraction 1990, p.723 - 728, 1992/00

no abstracts in English

Journal Articles

Extraction chromatography in the DHDECMP-HNO$$_{3}$$ system, II; Characteristics of the DHDECMP/XAD-4 resin on separation of trivalent actinide elements

Kimura, Takaumi; Akatsu, Jokun

Journal of Radioanalytical and Nuclear Chemistry, 149(1), p.25 - 34, 1991/00

 Times Cited Count:10 Percentile:72.11(Chemistry, Analytical)

no abstracts in English

Journal Articles

Extraction chromatography in the DHDECMP-HNO$$_{3}$$ system, I; Extraction behaviour of Ce(III) and Am(III) with the DHDECMP/XAD-4 resin

Kimura, Takaumi; Akatsu, Jokun

Journal of Radioanalytical and Nuclear Chemistry, 149(1), p.13 - 23, 1991/00

 Times Cited Count:17 Percentile:84.03(Chemistry, Analytical)

no abstracts in English

Journal Articles

Gamma ray assay of a waste drum for the determination of plutonium amount, III

Akatsu, Jokun; Kimura, Takaumi;

J. Inst. Nucl. Mater. Manage., 18(2), p.21 - 25, 1990/02

no abstracts in English

Journal Articles

Extraction chromatography in the DHDECMP(XAD-4)-HNO$$_{3}$$ system

Akatsu, Jokun; Kimura, Takaumi

Journal of Radioanalytical and Nuclear Chemistry, 140(1), p.195 - 203, 1990/00

 Times Cited Count:9 Percentile:67.09(Chemistry, Analytical)

no abstracts in English

Journal Articles

Dissolution of plutonium dioxide by electrolytic method, 1

Sakurai, Satoshi; Tachimori, Shoichi; Akatsu, Jokun; Kimura, Takaumi; Yoshida, Zenko; ; Yamashita, Toshiyuki; Ouchi, Kinji

Nihon Genshiryoku Gakkai-Shi, 31(11), p.1243 - 1250, 1989/11

 Times Cited Count:3 Percentile:41.84(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Non-destructive determination of spontaneously fissioning nuclides by neutron coincidence counting using multichannel time spectroscopy

Kimura, Takaumi; Goto, Hiroshi; Kobayashi, Yoshii; Akatsu, Jokun

Journal of Radioanalytical and Nuclear Chemistry, 125(1), p.29 - 40, 1988/00

 Times Cited Count:0 Percentile:0.02(Chemistry, Analytical)

no abstracts in English

JAEA Reports

Experience and projects for treatment, conditioning and strage of all radioactive wastes from Tokai Reprocessing Plant

Matsumoto, Kenichi*; Miyahara, Kenji; ; Asazuma, Shinichiro; Fukushima, Isao; Shoji, Kenji; Nojima, Yasuo; Kimura; Ikeda; Shibuya, Jun*; et al.

PNC TN8440 87-194, 82 Pages, 1987/08

PNC-TN8440-87-194.pdf:4.92MB

no abstracts in English

Journal Articles

Comments on neutron yields from actinide oxides; Authors' reply

; ; ;

Appl.Radiat.Isot., 38(2), P. 162, 1987/02

no abstracts in English

Journal Articles

Neutron yields from actinoide oxides

; ; ;

Appl.Radiat.Isot., 37(2), p.121 - 125, 1986/00

no abstracts in English

JAEA Reports

Studies on the dispersion of low-level liquid effluent released from the fuel reprocessing plant into the sea

*; *; *; Kitahara, Yoshihisa*; Kishimoto, Yoichiro; Yamato, Aiji; *; ; ; ; et al.

PNC TN841 78-69VOL1, 127 Pages, 1978/12

PNC-TN841-78-69VOL1.pdf:9.43MB

no abstracts in English

Journal Articles

Preparation of uranium-233

; ; *; ; Saeki, Masakatsu; ; Asano, Masaharu; ; B.Leugger*

Journal of Nuclear Science and Technology, 9(12), p.716 - 720, 1972/12

no abstracts in English

Oral presentation

Study on fast-neutron capture cross section by an activation method

Nakamura, Shoji; Toh, Yosuke; Kimura, Atsushi; Hatsukawa, Yuichi; Harada, Hideo; Ishiwatari, Yuki*; Saito, Isao*; Yasumi, Atsushi*; Mabuchi, Yukio*; Nakagawa, Tsutomu*; et al.

no journal, , 

no abstracts in English

Oral presentation

Origin identification of building stone using prompt $$gamma$$-ray analysis

Matsue, Hideaki; Ojima, Hitoshi*; Yoshida, Hirokazu*; Asano, Nobuko*; Hasegawa, Shoichi*; Cho, Akio*; Hatsukawa, Yuichi; Segawa, Mariko; Osawa, Takahito; Numao, Tatsuya*; et al.

no journal, , 

no abstracts in English

Oral presentation

Measurement of fast-neutron capture cross-section of $$^{99}$$Tc

Nakamura, Shoji; Hatsukawa, Yuichi; Toh, Yosuke; Kimura, Atsushi; Harada, Hideo; Ishiwatari, Yuki*; Yasumi, Atsushi*; Nakagawa, Tsutomu*; Mabuchi, Yukio*; Saito, Isao*; et al.

no journal, , 

Technetium-99 samples were irradiated by fast neutrons at YAYOI reactor. The fast-neutron capture cross-section was measured by the activation method.

Oral presentation

Measurement of fast-neutron capture cross-section of $$^{237}$$Np, 2; Irradiation in the Gz hole of YAYOI reactor

Nakamura, Shoji; Hatsukawa, Yuichi; Toh, Yosuke; Kimura, Atsushi; Harada, Hideo; Ishiwatari, Yuki*; Yasumi, Atsushi*; Nakagawa, Tsutomu*; Mabuchi, Yukio*; Saito, Isao*; et al.

no journal, , 

The $$^{237}$$Np sample was irradiated at the Gz hole of YAYOI reactor, and the fast-neutron capture cross-section was obtained by an activation method. The production amount of $$^{238}$$Np was measured by $$gamma$$-ray spectroscopy. The neutron flux at the irradiation position was monitored by a gold foil. It was found that the present result of the fast-neutron capture cross-section was 15% larger than that in JENDL-3.3.

Oral presentation

Measurement of fast-neutron capture cross-section of $$^{129}$$I

Nakamura, Shoji; Toh, Yosuke; Hatsukawa, Yuichi; Kimura, Atsushi; Harada, Hideo; Yasumi, Atsushi*; Nakagawa, Tsutomu*; Mabuchi, Yukio*; Saito, Isao*; Ishiwatari, Yuki*

no journal, , 

The fast-neutron capture cross section of $$^{129}$$I was measured at the YAYOI reactor by the activation method. The amount of $$^{130}$$I was obtained by measuring $$gamma$$-rays emitted from $$^{130}$$I. The neutron flux was monitored by a piece of gold foil. The fast-neutron capture cross section was derived from the information of the production amount of $$^{130}$$I and the neutron flux. This work found that the evaluated data might be overestimated by about 10% and more.

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