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Journal Articles

Measurement of Neutron Capture Cross Section of $$^{237}$$Np from 0.02 to 100 eV

Shcherbakov, O.; Furutaka, Kazuyoshi; Nakamura, Shoji; Sakane, Hitoshi; Katsuhei, Kobayashi,*; Yamamoto, Shuji*; Harada, Hideo

Journal of Nuclear Science and Technology, 42(2), p.135 - 144, 2005/00

 Times Cited Count:23 Percentile:82.08(Nuclear Science & Technology)

The neutron capture cross section of Np-237 has been measured in the energy range of 0.02 eV - 100 eV. For the first time, the capture cross section of Np-237 was measured using the total energy $$gamma$$-ray detector. The results have been compared with evaluated nuclear data libraries.

Journal Articles

Measurement of neutron capture cross sections for radioactive nuclei

Harada, Hideo; Nakamura, Shoji; Furutaka, Kazuyoshi; Shcherbakov, O.; Sakane, Hitoshi; Kobayashi, Katsuhei*; Yamamoto, Shuji*

KURRI Progress Report 2003, P. 171, 2004/09

Researches and developments done at Research Reactor Institute of Kyoto University in FY2003 are summarized. Researches on measurement of neutron capture cross sections by activation method, development of a method to determine thermal neutron capture cross section by prompt $$gamma$$-ray measurements, and neutron capture cross section measurements by Time-of-Flight method are briefly mentioned.

Journal Articles

Measurement of the Np-237 Neutron Capture Cross Section from Thermal to 100 eV

Shcherbakov, O.; Harada, Hideo; Furutaka, Kazuyoshi; Nakamura, Shoji; Sakane, Hitoshi; Katsuhei, Kobayashi,*; Yamamoto, Shuji*

ND2004 Abstracts, LA-UR-04-5900, p.133, 133 Pages, 2004/09

The neutron capture cross section of Np-237 has been measured for the energy range between thermal to 100 eV using a TOF method. The developed system composed of JNC-BGO detector and FADC data taking is presented together with the obtained result.

Journal Articles

Measurement of the Np-237 Neutron Capture Cross Section from Thermal to 100 eV

Shcherbakov, O.; Harada, Hideo; Furutaka, Kazuyoshi; Nakamura, Shoji; Sakane, Hitoshi; Kobayashi, Katsuhei*; Yamamoto, Shuji*

AIP Conference Proceedings 769, p.1007 - 1010, 2004/00

The neutron capture cross section of Np-237 has been measured relative to the B-10(n,alpha)Li-7 cross section in the energy range from 0.02 to 100 eV. The measurements were carried out by the time-of-flight method using the 8.54 liters BGO scintillator as a 4-pi capture $$gamma$$ ray detector and the 46 MeV Linac as a pulsed neutron source. The results of present measurements have been compared with experimental data of other authors and evaluated data.

Journal Articles

A BGO detector system for studies of neutron capture by radioactive nuclides

Shcherbakov, O.; Furutaka, Kazuyoshi; Nakamura, Shoji; Harada, Hideo; Kobayashi, Katsuhei*

Nuclear Instruments and Methods in Physics Research A, 517, 269 Pages, 2004/00

 Times Cited Count:9 Percentile:52.73(Instruments & Instrumentation)

None

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.

Journal Articles

Measurements of neutron induced fission cross-section for $$^{242m}$$Am from 0.003eV to 10keV using lead slowing-down spectrometer, thermal neutron facility and time-of-flight method

Kai, Tetsuya; Kobayashi, Katsuhei*; Yamamoto, Shuji*; Cho, H.*; Fujita, Yoshiaki*; Kimura, Itsuro*; Okawachi, Yasushi*; Wakabayashi, Toshio*

Annals of Nuclear Energy, 28(8), p.723 - 739, 2001/05

 Times Cited Count:7 Percentile:48.69(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Int. Conf. on Nuclear Data for Science and Technology

Shibata, Keiichi; Fukahori, Tokio; Takano, Hideki; *; Watanabe, Yukinobu*; Kobayashi, Katsuhei*; *; Oyamatsu, Kazuhiro*

Nihon Genshiryoku Gakkai-Shi, 39(10), p.863 - 865, 1997/00

no abstracts in English

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