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NSR database version of May 19, 2024.

Search: Author = T.Matsuhashi

Found 3 matches.

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2015KA08      Phys.Rev. C 91, 037603 (2015)

T.Katabuchi, T.Matsuhashi, K.Terada, M.Igashira, M.Mizumoto, K.Hirose, A.Kimura, N.Iwamoto, K.Y.Hara, H.Harada, J.-i.Hori, T.Kamiyama, K.Kino, F.Kitatani, Y.Kiyanagi, S.Nakamura, Y.Toh

Misassigned neutron resonances of 142Nd and stellar neutron capture cross sections

NUCLEAR REACTIONS 141Pr, 142Nd(n, γ), E<2.5 keV; measured time-of-flight spectra, Eγ, Iγ; deduced resonances, resonance parameters, capture yield TOF spectra. Previous six resonances from 218.6 to 1485 eV assigned to 142Nd reassigned to 141Pr. Measurements using spallation neutron source and the Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) at Japan Proton Accelerator Research Complex (J-PARC). Calculated Maxwellian-averaged neutron capture cross section of 142Nd and compared with JENDL-4.0 parameters.

doi: 10.1103/PhysRevC.91.037603
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Data from this article have been entered in the XUNDL database. For more information, click here.

2014KA39      Nucl.Data Sheets 119, 398 (2014)

T.Katabuchi, T.Matsuhashi, K.Terada, M.Mizumoto, K.Hirose, A.Kimura, K.Furutaka, K.Y.Hara, H.Harada, J.Hori, M.Igashira, T.Kamiyama, F.Kitatani, K.Kino, Y.Kiyanagi, M.Koizumi, S.Nakamura, M.Oshima, Y.Toh

A New Signal Processing Technique for Neutron Capture Cross Section Measurement Based on Pulse Width Analysis

NUCLEAR REACTIONS 197Au(n, γ), E=0.01-1000 eV; measured Eγ, Iγ using large-volume NaI(Tl); deduced σ; calculated σ using JENDL-4.0 resonance parameters.

doi: 10.1016/j.nds.2014.08.111
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2014TE04      Nucl.Data Sheets 119, 147 (2014)

K.Terada, T.Matsuhashi, B.Hales, T.Katabuchi, M.Igashira

Measurements of keV-neutron Capture Cross Sections and Capture Gamma-ray Spectra of Pd Isotopes

NUCLEAR REACTIONS 104,105,106,108,110Pd, 197Au(n, γ), E=15-100 keV; measured Eγ, Iγ using large anti-Compton NaI(Tl) spectrometer with ToF; deduced σ, γ-ray spectra at fixed neutron energy. Compared with other data, ENDF/B-VII.1 and JENDL-4.0.

doi: 10.1016/j.nds.2014.08.041
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset23187.

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