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Journal Articles

Measurements of thermal-neutron capture cross-section and resonance integral of neptunium-237

Nakamura, Shoji; Kitatani, Fumito; Kimura, Atsushi; Uehara, Akihiro*; Fujii, Toshiyuki*

Journal of Nuclear Science and Technology, 56(6), p.493 - 502, 2019/06

The thermal-neutron capture cross-section($$sigma_{0}$$)and resonance integral(I$$_{0}$$) were measured for the $$^{237}$$Np(n,$$gamma$$)$$^{238}$$Np reaction by an activation method. A method with a Gadolinium filter, which is similar to the Cadmium difference method, was used to measure the $$sigma_{0}$$ with paying attention to the first resonance at 0.489 eV of $$^{237}$$Np, and a value of 0.133 eV was taken as a cut-off energy. Neptunium-237 samples were irradiated at the pneumatic tube of the Kyoto University Research Reactor in Institute for Integral Radiation and Nuclear Science, Kyoto University. Wires of Co/Al and Au/Al alloys were used as monitors to determine thermal-neutron fluxes and epi-thermal Westcott's indices at an irradiation position. A $$gamma$$-ray spectroscopy was used to measure activities of $$^{237}$$Np, $$^{238}$$Np and neutron monitors. On the basis of Westcott's convention, the $$sigma_{0}$$ and I$$_{0}$$ values were derived as 186.9$$pm$$6.2 barn, and 1009$$pm$$90 barn, respectively.

Journal Articles

Proton-induced activation cross section measurement for aluminum with proton energy range from 0.4 to 3 GeV at J-PARC

Matsuda, Hiroki; Meigo, Shinichiro; Iwamoto, Hiroki

Journal of Nuclear Science and Technology, 55(8), p.955 - 961, 2018/08

 Times Cited Count:1 Percentile:38.14(Nuclear Science & Technology)

We have started an experimental program to measure activation cross sections systematically in the proton-induced spallation reaction in structural materials commonly used in high-intensity proton accelerator-based facilities, such as Japan Proton Accelerator Research Complex (J-PARC). As the first step of the program, aluminum (Al) was chosen to verify the adequacy of the measurement technique implemented in a J-PARC proton beam environment because data of Al have been relatively well studied both by experimental measurement and simulation. Activation cross sections of $$^{7}$$Be, $$^{22}$$Na, and $$^{24}$$Na in Al were measured at proton energy points from 0.4, 1.3, 2.2 to 3.0 GeV, which could be delivered smoothly from the synchrotron. The validity of experimental data has been verified by introducing an effective proton numbers determination procedure. We compared the measured data with existing experimental data, the evaluated data (JENDL-HE/2007), and the calculations with several intra-nuclear cascade models by the Particle and Heavy Ion Transport code System (PHITS) code. Although the experimental data agreed with JENDL-HE/2007, the calculations underestimated about 40%. This could come from the evaporation model (generalized evaporation model) being implemented in the PHITS code. We found that the calculations agreed with the experimental data by an upgraded PHITS code.

Journal Articles

Activation measurements of neputunium-237 at KURRI-Linac

Nakamura, Shoji; Terada, Kazushi; Shibahara, Yuji*; Uehara, Akihiro*; Fujii, Toshiyuki*; Sano, Tadafumi*; Takahashi, Yoshiyuki*; Hori, Junichi*

KURRI Progress Report 2015, P. 67, 2016/08

The activation measurements of Np-237 were performed with neutron sources at KURRI-Linac. It was found that activation measurements supported the evaluated cross-section data of JENDL-4.0.

Journal Articles

Measurements of americium isotopes by activation method at KURRI-Linac

Nakamura, Shoji; Terada, Kazushi; Takahashi, Yoshiyuki*; Sano, Tadafumi*; Hori, Junichi*

KURRI Progress Report 2015, P. 69, 2016/08

Neutron capture cross section measurements has been conducted for Minor Actinides (MAs) under the research project entitled by "Research and development for Accuracy Improvement of neutron nuclear data on Minor ACtinides (AIMAC)". The present work selected two americium isotopes, $$^{241}$$Am and $$^{243}$$Am, were selected, and measurements were carried out by an activation method with neutron sources at KURRI-Linac. It was found that the neutron flux at the target positon was of the order of 10$$^{8}$$ (n/cm$$^{2}$$s). The reaction rates of $$^{241}$$Am and $$^{243}$$Am were obtained by $$alpha$$- and $$gamma$$-ray measurements of the irradiated Am samples.

Journal Articles

Development of multi-group neutron activation cross-section library for decommissioning of nuclear facilities

Okumura, Keisuke; Kojima, Kensuke; Tanaka, Kenichi*

JAEA-Conf 2015-003, p.43 - 47, 2016/03

In the safety assessment concerning disposal of radioactive wastes generated in the decommissioning of nuclear facilities, it is necessary to evaluate the radionuclide inventory produced by the activation of structured materials. For this purpose, we have to pay much attention to the activation of many impurities irradiated in various neutron spectra depending on their positions and materials. Therefore, accurate activation cross-section data are necessary for many nuclides and reactions. A new multi-group neutron activation cross-section library (MAXS) was developed based on the recent nuclear data JENDL-4.0 and JEFF-3.0/A to apply it to the activation calculations for the decommissioning of nuclear facilities. The library contains cross-sections and isomeric ratios for many reactions such as (n,$$gamma$$), (n,f), (n,2n), (n,3n), (n,p), (n,$$alpha$$), (n,d), (n,t), (n,n$$alpha$$), (n,np), and so on, for 779 nuclides, in the 199-energy group structure of VITAMIN-B6.

Journal Articles

Measurements of deuteron-induced activation cross sections for IFMIF accelerator structural materials in the energy range of 22-40 MeV

Ochiai, Kentaro; Nakao, Makoto*; Hori, Junichi*; Sato, Satoshi; Yamauchi, Michinori*; Ishioka, Noriko; Nishitani, Takeo

Fusion Engineering and Design, 81(8-14), p.1459 - 1464, 2006/02

 Times Cited Count:2 Percentile:79.37(Nuclear Science & Technology)

The IFMIF consists of two 40 MeV deuteron linear accelerators with 125 mA beam current each. The structure materials of the accelerators are activated with high energetic deuteron. To measure the activation cross sections with $$^{27}$$Al, $$^{rm nat}$$Cu, $$^{rm nat}$$W, $$^{rm nat}$$V, $$^{rm nat}$$Ni, $$^{rm nat}$$Fe, and $$^{rm nat}$$Ta samples irradiated with 22-40 MeV deuteron beams, we have carried out the irradiation experiment of the main elements of the IFMIF candidate materials by using the deutron beam of the AVF cyclotron of the TIARA facility in JAERI/Takasaki.

Journal Articles

Measurements of deuteron-induced activation cross sections for IFMIF accelerator structural materials

Nakao, Makoto*; Hori, Junichi*; Ochiai, Kentaro; Sato, Satoshi; Yamauchi, Michinori*; Ishioka, Noriko; Nishitani, Takeo

Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2004), p.1489 - 1492, 2004/09

no abstracts in English

JAEA Reports

DCHAIN-SP 2001: High energy particle induced radioactivity calculation code

Kai, Tetsuya; Maekawa, Fujio; Kosako, Kazuaki*; Kasugai, Yoshimi; Takada, Hiroshi; Ikeda, Yujiro

JAERI-Data/Code 2001-016, 82 Pages, 2001/03

JAERI-Data-Code-2001-016.pdf:4.22MB

no abstracts in English

Journal Articles

Experimental validation of decay heat calculation codes and associated nuclear data libraries for fusion energy

Maekawa, Fujio; Wada, Masayuki*; Ikeda, Yujiro

Journal of Nuclear Science and Technology, 38(1), p.53 - 62, 2001/01

no abstracts in English

Journal Articles

Production of a dosimetry cross section set up to 50MeV

Maekawa, Fujio; Von-Moellendorff, U.*; Wilson, P. P. H.*; Wada, Masayuki*; Ikeda, Yujiro

Reactor Dosimetry: Radiation Metrology and Assessment (ASTM STP 1398), p.417 - 424, 2001/00

no abstracts in English

Journal Articles

Experimental study on beryllium-7 production via sequential reactions in lithium-containing compounds irradiated by 14-MeV neutrons

Maekawa, Fujio; Verzilov, Y.M.*; Smith, D. L.*; Ikeda, Yujiro

Journal of Nuclear Materials, 283-287(Part.2), p.1448 - 1452, 2000/12

 Times Cited Count:5 Percentile:58.19

no abstracts in English

Journal Articles

The IRAC code system to calculate activation and transmutation in the TIARA Facility

Tanaka, Susumu; Fukuda, Mitsuhiro; Nishimura, Koichi; Hosono, Masakazu; Watanabe, Hiromasa; Yamano, Naoki*

Journal of Nuclear Science and Technology, 37(Suppl.1), p.840 - 844, 2000/03

no abstracts in English

Journal Articles

Measurements of neutron spallation cross sections of $$^{12}$$C and $$^{209}$$Bi in the 20- to 150-MeV energy range

E.Kim*; Nakamura, Takashi*; *; Uwamino, Y.*; *; Imamura, Mineo*; Nakao, Noriaki*; *;

Nuclear Science and Engineering, 129(3), p.209 - 223, 1998/00

 Times Cited Count:57 Percentile:2.76(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

IRACM: A Code system to calculate induced radioactivity produced by ions and neutrons

; Fukuda, Mitsuhiro; ; Watanabe, Hiromasa; Yamano, Naoki*

JAERI-Data/Code 97-019, 91 Pages, 1997/05

JAERI-Data-Code-97-019.pdf:2.58MB

no abstracts in English

Journal Articles

Measurements of the $$^{32}$$S(n,p)$$^{32}$$P and $$^{35}$$Cl(n,$$alpha$$)$$^{32}$$P reaction cross sections in the energy range of 13.3-14.9MeV and their integral test below 14MeV

Y.M.Verzilov*; Maekawa, Fujio; Oyama, Yukio; Ikeda, Yujiro

Fusion Engineering and Design, 37(1), p.95 - 105, 1997/00

 Times Cited Count:6 Percentile:49

no abstracts in English

Journal Articles

Measurements of activation cross sections for waste management assessment in fusion reactors

Ikeda, Yujiro; D.L.Smith*

Fusion Technology, 30(3(PT.2B)), p.1190 - 1196, 1996/12

no abstracts in English

Journal Articles

Measurement of the thermal neutron cross section of the $$^{90}$$Sr(n,$$gamma$$)$$^{91}$$Sr reaction

Harada, Hideo*; Sekine, Toshiaki; ; ; Kobayashi, Katsutoshi; Otsuki, Tsutomu*; Kato, Toshio*

Journal of Nuclear Science and Technology, 31(3), p.173 - 179, 1994/03

 Times Cited Count:22 Percentile:13.21(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Measurement of neutron activation cross sections for the $$^{99}$$Tc(n,p)$$^{99}$$Mo, $$^{99}$$Tc(n,$$alpha$$)$$^{96}$$Nb, $$^{99}$$Tc(n,n$$alpha$$)$$^{95}$$Nb, and $$^{99}$$Tc(n,n)$$^{99m}$$Tc reactions at 13.5 and 14.8MeV

Ikeda, Yujiro; E.T.Cheng*; Konno, Chikara; Maekawa, Hiroshi

Nuclear Science and Engineering, 116, p.28 - 34, 1994/01

 Times Cited Count:5 Percentile:49.82(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of IRAC code system to calculate induced radioactivity produced by ions and neutrons

Tanaka, Susumu; Fukuda, Mitsuhiro; ; Yokota, Wataru; Kamiya, Tomihiro; Watanabe, Hiromasa; Yamano, Naoki*; ;

Proc. of the 8th Int. Conf. on Radiation Shielding, 0, p.965 - 971, 1994/00

no abstracts in English

JAEA Reports

Activation cross section measurements at neutron energy from 13.3 to 14.9MeV using the FNS facility

Konno, Chikara; Ikeda, Yujiro; *; Kawade, Kiyoshi*; Yamamoto, Hiroshi*; Maekawa, Hiroshi

JAERI 1329, 105 Pages, 1993/10

JAERI-1329.pdf:3.54MB

no abstracts in English

24 (Records 1-20 displayed on this page)