Refine your search:     
Report No.
 - 
Search Results: Records 1-16 displayed on this page of 16
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

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

Neutron capture cross section measurement of I-129 with lead slowing-down spectrometer

*

JNC TJ9400 2001-021, 84 Pages, 2002/02

JNC-TJ9400-2001-021.pdf:2.79MB

Making use of the neutron time-of-flight (TOF) method with an electron linear accelerator (linac) and of a lead slowing-down spectrometer (KULS), we havc measured nuclear data of minor actinidcs (MAs) and/or long-lived fission products (LLFPs). In the present study, we have carried out the capture cross section measurement of $$^{129}$$I by the linac TOF method as a part of experimental series for LLFP. At first, the experimental data and the evaluated data (ENDF/B-VI, JENDL-3.2, and JEF-2.2) of $$^{129}$$I have been reviewed. As a result, it has been found that the present status of the $$^{129}$$I data is not enough in quality and quantity. Secondly, by using the NaI-129 sample, the $$^{129}$$I (n, $$gamma$$) $$^{130}$$I cross section has been measured from 0.004 eV to 10 keV relative to the $$^{10}$$B (n, $$alpha$$) reaction with a pail of C$$_{6}$$ D$$_{6}$$ scintillation detectors. After the background subtraction and the self-shielding collection, the cross section has been normalized to the well-known reference cross section (27.04b) at 0.0253 eV. The data measured by Macklin from 3 to 400 keV and the data evaluated in ENDF/B-Vl are in good agreement with the present measurement in general. However, the evaluated values from a few eV to about 60 eV in JENDL-3.2 and JEF-2.2 are obviously low comparing to the measurement and the ENDF/B-Vl values. We could provide the interesting and the useful data for the $$^{129}$$I (n, $$gamma$$) $$^{130}$$I reaction in the lower/resonance energy region.

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

JAEA Reports

Neutron capture cross section measurement of Tc-99 with lead slowing-down spectrometer

*

JNC TJ9400 2001-003, 66 Pages, 2001/02

JNC-TJ9400-2001-003.pdf:1.99MB

The present status of nuclear data for technetium(Tc)-99, which is a well-known long-lived fission product (LLFP), has been reviewed. Making use of the neutron time-of-flight (TOF) method with a 46 MeV electron linear accelerator (linac) of the Kyoto University Research Reactor Institute (KURRI), the $$^{99}$$Tc (n, $$gamma$$) $$^{100}$$Tc cross section has been measured from 0.01eV to 10keV relative to the $$^{10}$$B (n, $$alpha$$) reaction with a pair of C$$_{6}$$ D$$_{6}$$ liquid scintillation detectors. After the neutron self-shielding correction for the Tc-99 sample, the cross section has been normalized at 0.0253eV to the well-known reference cross section value. The existing experimental data and the evaluated data in ENDF/B-VI and JENDL-3.2 are in general agreement with the current measurement, although the evaluations seem to be lower than the measurement in the valley regions of the resonance cross section. The Kyoto University Lead slowing-down Spectrometcr (KULS) has been also applied to the capture cross section measurement from 0.25eV to 300eV with an Ar-gas proportional counter. The neutron flux/spectrum in the KULS has been measured with a BF$$_{3}$$ proportional counter. The result obtained has been also normalized at 0.35eV to the well-known reference cross section. The same tendency as the result with the current TOF measurement can be seen with the KULS measurement in comparison of the earlier measurements and the evaluated values. The KULS data are close to those obtained by energy-broadening the TOF data. Finally, the preliminaly result of the neutron activation experiment with the Tc-99 sample is presented.

JAEA Reports

Preliminary experiment of neutron capture cross section of Tc-99 with lead slowing-down spectrometer

*

JNC TJ9400 2000-009, 63 Pages, 2000/02

JNC-TJ9400-2000-009.pdf:2.48MB

The present status of nuclear data for technetium (Tc)-99, which is a well-known fission product (FP), has been reviewed and investigated. And making use of the Kyoto university Lead Slowing-down Spectrometer (KULS), the cross section of the $$^{99}$$Tc (n, $$gamma$$) $$^{100}$$Tc reaction has been measured in the energy range from thermal to keV neutron energy with an Ar-gas proportinal counter. The neutron flux/spectrum has been monitored with a BF$$_{3}$$ proportional counter, and the relative measurement has been normalized to the well-known standard capture cross section value for the $$^{99}$$Tc (n, $$gamma$$) $$^{100}$$Tc reaction at 0.0253 eV. Self-shielding corrections, especially near the resonance peaks, were made by the calculations with the MCNP code. Although the experimental data measured by Chou et al with a lead slowing-down spectrometer are higher in general, the energy dependency is similar to the present measurement. The evaluated data in ENDF/B-VI and JENDL-3.2 are higher near the resonances at 5.6 and 20 eV and above several 100 eV. A lead slowing-down spectrometer was installed coupled to a 46 MeV electron linac at the Research Reactor Institute, Kyoto university (KURRI). Characteristics of the Kyoto University Lead Slowing-down Spectrometer (KULS) were measured and (1)the relation between neutron slowing-down time t($$mu$$s) and energy E(keV) (E=190/t$$^{2}$$ in Bi hole and E=156/t$$^{2}$$ in Pb hole) and (2)the energy resolution ($$sim$$40% in Bi and Pb holes) were experimentally investigated. (3)The neutron energy spectrum in the KULS was also measured by the neutron TOF method. The results obtained by the MCNP code were in general agreement with these experimental ones.

JAEA Reports

Neutron capture cross section measurement of Np-237 with lead slowing-down spectrometer

*

JNC TJ9400 99-004, 97 Pages, 1999/03

JNC-TJ9400-99-004.pdf:3.73MB

The present status of nuclear data for neptuniumu(Np)-237, which is a well-known minor actinide, has been reviewed and investigated. Making use of the Kyoto University Lead Slowing-down Spectrometer, the neutron capture cross sections of Au-197 and Np-237 have been measured in the energy range from thermal to keV energy neutrons with an Ar-gas proportional counter. The neutron flux/spectrum has been monitored with a BF$$_{3}$$ proportional counter, and the relative measurement has been normalized to the well-known standard capture cross section value at 0.0253 eV. Self-shielding corrections, especially near the resonance peaks, were made by the calculations with the MCNP code. The evaluated cross sections for the $$^{197}$$Au(n,$$gamma$$) $$^{198}$$Au and $$^{237}$$Np(n,$$gamma$$) $$^{238}$$Np reactions in ENDF/B-VI and JENDL-3.2 are in general agreement with the measurements, although the experimental values are rather lower at the resonance peaks. A lead slowing-down spectrometer was installed coupled to the 46 MeV electron linac at Research Reactor Institute, Kyoto University (KURRI). Characteristics of the Kyoto University Lead Slowing-down Spectrometer (KULS) were measured and (1) the relation between neutron slowing-down time t($$mu$$s) and energy E (keV) (E=190/t$$^{2}$$ in Bi hole and E=156/t$$^{2}$$ in Pb hole) and (2) energy resolution ($$sim$$40% in Bi and Pb holes) were experimentally investigated. (3)The neutron energy spectrum in the KULS was also measured by the neutron TOF method. The results obtained by the MCNP code were in general agreement with these experimental ones.

JAEA Reports

Measurement of nuclear data for minor actinides with lead slowing-down spectrometer - III

*

PNC TJ9604 97-001, 108 Pages, 1997/03

PNC-TJ9604-97-001.pdf:4.05MB

A lead slowing-down spectrometer was installed coupled to the 46 MeV electron linac at Research Reactor Institute, Kyoto university (KURRI). Characteristics of the Kyoto University Lead Slowing-down Spectrometer (KULS) were measured for (1)the relation between neutron slowing-down time t($$mu$$s) and energy E (keV) (E=190/t$$^{2}$$ in Bi hole and E=156/$$^{2}$$ in Pb hole), (2)energy resolutlon ($$sim$$40 % in Bi and Pb holes), and (3)neutron energy spectrum by the neutron TOF method. The results obtained by the MCNP code were in general agreement with these experimental ones. The KULS has been applied to the fission cross section measurements of Am-241, Am-243 and Am-242m relative to that of U-235 from $$sim$$0.1 eV to $$sim$$10 keV, making use of the back-to-back type double fission chambers. For Am-241, Dabbs and ENDF/B-VI data are in good agreement with the present measurement. The JEND L-3.2 data are smaller by a factor of 2 between 10 and 200 eV. The ENDF/B-VI data for Am-243 are lower between 15 and 60 eV, and the JENDL-3.2 are lower in general above 100 eV. It has been found that the preliminary result for the Am-242m(n,f) reaction is close to the ENDF/B-VI and the JENDL-3.2 data. Thermal neutron cross sections for Am-241 and Am-243 have also been measured in a standard Maxwellian distribution spectrum field. Finally, aiming at the measurement of capture cross section for MA nuclides, the experimental investigation for Np-237 sample ($$sim$$2 mg) has been performed with the KULS. Due to the comparable background counts to the foreground ones, the capture events from the sample have scarecely been detected with an Ar-gas proportional counter.

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

JAEA Reports

JENDL dosimetry file

Nakazawa, Masaharu*; *; *; Iguchi, Tetsuo*; Sakurai, Kiyoshi; Ikeda, Yujiro; Nakagawa, Tsuneo

JAERI 1325, 132 Pages, 1992/03

JAERI-1325.pdf:3.64MB

no abstracts in English

Journal Articles

Self-shielding factors for neutron capture reactions of uranium-238 and thorium-232 in energy range of 1$$sim$$35keV

Oigawa, Hiroyuki; Fujita, Yoshiaki*; *; Yamamoto, Shuji*; Kimura, Itsuro*

Journal of Nuclear Science and Technology, 28(10), p.879 - 893, 1991/10

no abstracts in English

Journal Articles

Calculation of the activation rate of a cylindrical sample irradiated by a cylindrical fast neutron source

; ; *; Kimura, Itsuro*

Nuclear Instruments and Methods, 116(2), p.361 - 364, 1974/02

no abstracts in English

16 (Records 1-16 displayed on this page)
  • 1