Measurement of Double Differential Neutron Emission Cross Sections for Incident Neutrons of 14 MeV

Takahashi, Akito; Ichimura, E.; Sasaki, Yasuhiro; Sugimoto, Hisashi

doi:10.1080/18811248.1988.9733582

Cited by 43 publications

(15 citation statements)

References 5 publications

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“…This treatment modifies the shapes of preequilibrium spectra. It is found from the figure that the present evaluation is in good agreement with the data measured by Takahashi et al [49]. The ENDF/B-VII.1 evaluation obviously underestimates the experiment around 12 MeV.…”

Section: Comparison With Experimental and Other Evaluated Data In Fassupporting

confidence: 81%

Evaluation of neutron nuclear data on antimony isotopes

Shibata

2014

Journal of Nuclear Science and Technology

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Neutron nuclear data on 121,123,124,125,126 Sb have been evaluated for the next version of JENDL general purpose file in the energy region from 10 −5 eV to 20 MeV. In the low-energy region, the latest resolved resonance parameters were taken into account for 121, 123 Sb. The thermal capture cross sections of 125, 126 Sb, for which no measurements exist, were determined by using a simplified formula. The statistical model was applied to calculate the cross sections above the resolved resonance region. In the calculations, coupledchannel optical model parameters were used for the interaction between neutrons and odd-mass targets. Preequilibrium and direct-reaction processes were considered in addition to the compound process. The present evaluation is consistent with available experimental data. The evaluated data are compiled into an ENDF-formatted data file.

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Section: Comparison With Experimental and Other Evaluated Data In Fassupporting

confidence: 81%

Evaluation of neutron nuclear data on antimony isotopes

Shibata

2014

Journal of Nuclear Science and Technology

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“…The present calculations reproduce the spectra measured by Takahashi et al 36) above 7 MeV. In the low energy region below 7 MeV, the present calculations as well as all the evaluated data are somewhat larger the experimental data.…”

Section: Elemental Datasupporting

confidence: 79%

Calculation of Neutron Nuclear Data on Calcium Isotopes for JENDL-4

Shibata

2007

Journal of Nuclear Science and Technology

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ÃÃNeutron nuclear data on 40;42;43;44;46;48 Ca have been calculated for the evaluated nuclear data library JENDL-4. Simultaneously calculated are the total, elastic and inelastic scattering, ðn; pÞ, ðn; Þ, ðn; Þ, ðn; 2nÞ, ðn; 3nÞ, ðn; npÞ and ðn; nÞ reaction cross sections, the angular distributions of emitted neutrons, and the energy distributions of emitted particles and -rays. The statistical model was applied to calculate these quantities. Pre-equilibrium and direct-reaction processes were taken into account in addition to the compound process. It is found that the present calculations are almost consistent with available experimental data and much better than the JENDL-3.3 evaluation. In particular, the measured -ray production data are well reproduced by the present calculations.

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“…[1][2][3][4][5] Detailed measurements of -particle emission DDX are, however, quite few and are still insufficient. The measurement of -particle emission DDX is fundamentally difficult because a thin sample material has to be used to prevent energy loss of emitted -particles in the sample despite relatively small cross sections.…”

Section: Introductionmentioning

confidence: 99%

Measurement and Analysis of Neutron-Induced Alpha Particle Emission Double-Differential Cross Section of Carbon at 14.2 MeV

Kondo

Murata

Ochiai

et al. 2008

J. Nucl. Sci. Technol.

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We carried out a detailed measurement of the neutron-induced -particle emission double-differential cross section of carbon at 14.2 MeV, for which there are few measured data in spite of its importance in many applications. In our measurement, a superior S/N ratio, high angular/energy resolutions and a wide detection energy range were realized with a pencil DT neutron beam and a countertelescope system. The obtained cross section for the 12 C(n, 0 ) 9 Be (ground state) reaction agreed well with the results of previous experiments and evaluated nuclear data. The obtained angular-differential cross section of the 12 C(n,n 0 +3) reaction for -particles showed a strong forward-peaked distribution that suggested a significant contribution of the direct reaction process to the 3 breakup. We attempted to calculate the emitted particle spectra by a Monte Carlo method and estimate the branching ratio of the channels that contribute to the 12 C(n,n 0 +3) reaction. As a result, it was found that the 12 C(n,) 9 Be Ã channels play an important role in generating the experimental double-differential cross section both of emitted -particles and neutrons. The estimated ratio of the 12 C(n,) 9 Be Ã channels was approximately 40%, somewhat larger than those evaluated in previous studies.

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Measurement of Double Differential Neutron Emission Cross Sections for Incident Neutrons of 14 MeV

Cited by 43 publications

References 5 publications

Evaluation of neutron nuclear data on antimony isotopes

Evaluation of neutron nuclear data on antimony isotopes

Calculation of Neutron Nuclear Data on Calcium Isotopes for JENDL-4

Measurement and Analysis of Neutron-Induced Alpha Particle Emission Double-Differential Cross Section of Carbon at 14.2 MeV

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