Measurement of double differential neutron emission cross sections for incident neutrons of 14MeV.

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

doi:10.3327/jnst.25.215

Cited by 11 publications

(4 citation statements)

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“…The uncertainty in the present measurement calculated with the help of covariance analysis was found to be 15%. The measurement has been compared with the literature data [6][7][8][9][10] , JEFF-3.3 21 , ENDF/B-VII.1 22 and the theoretical modular code TALYS-1.8 and TALYS-1.9 11 . A comparison of the present result shows a good agreement with literature data Frehaut et al 9 as well as with ldmodel-3 of the TALYS-1.9 11 code.…”

Section: Discussionmentioning

confidence: 99%

“…Tantalum is a candidate material of the spallation target 5 to be used for accelerator driven subcritical systems (ADSs). The cross-section of 181 Ta(n,2n) 180 Ta reaction around 14 MeV has been reported by various authors [6][7][8][9][10] , but most of them were obtained before 1992, furthermore, there was disagreement in those data with theoretical nuclear code TALYS-1.8 and TALYS-1.9 11 . The natural tantalum consists of two isotopes, namely, 180m Ta (0.012%) and 181 Ta (99.988%).…”

Section: Introductionmentioning

confidence: 99%

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Measurements of 181Ta(n,2n)180Ta reaction cross-section at the neutron energy of 14.78 MeV

2020

IJPAP

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The cross-section of the 181 Ta(n,2n) 180 Ta reaction has been measured with respect to the 197 Au(n,2n) 196 Au monitor reaction at the incident neutron energy of 14.78± 0.20 MeV, using neutron activation analysis and off-line γ-ray spectrometric technique. The present measurement has been done at the energy where discrepant measured results are available in the EXFOR data library. The result has been compared with evaluated data libraries JEFF-3.3 and ENDF/B-VII.1. The present result has also been supported by theoretical predictions of nuclear model code TALYS1.8 and TALYS-1.9. The uncertainty and the correlations among the measured cross-section has been studied using co-variance analysis.

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Section: Discussionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Measurements of 181Ta(n,2n)180Ta reaction cross-section at the neutron energy of 14.78 MeV

2020

IJPAP

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“…The total sample mass and the apparent density of the Nb sample were 48.7 kg and 4.39 g/cm 3 , respectively. This density is equivalent that the sample has 1.1 mean free paths for 14 MeV neutrons.…”

Section: Nb Sample Pilementioning

confidence: 99%

“…Among them, JENDL-3.2 1) from Japan Atomic Energy Research Institute (JAERI), Japan and ENDF/B-VI 2) from BNL, USA are widely accepted as standard nuclear data files, as both of them are based on recent measurements and new neutron reaction theory. Especially, the accumulation of double differential cross section (DDX) measurements 3,4) has been adopted in these data files. In addition, European Community (EC) and IAEA Nuclear Data Section (IAEA-NDS) have published their own data files, EFF-2 5) and FENDL-2, 6) respectively.…”

Section: Introductionmentioning

confidence: 99%

Measurement of Leakage Neutron Spectra from a Spherical Pile of Niobium Bombarded with 14MeV Neutrons and Validation of Its Nuclear Data

Ichihara

Hayashi

Kimura³

et al. 2001

Journal of Nuclear Science and Technology

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For validation of nuclear data files for Nb, the absolute leakage neutron spectrum from a spherical pile of Nb was measured in the energy range between 0.1 and 16 MeV at OKTAVIAN. A sensitivity analysis was performed with MCNP-4A and the modified JENDL-3.2 libraries. The measured spectrum was compared with the MCNP-4A calculation with two nuclear data libraries processed from JENDL-3.2 and ENDF/B-VI. The comparison was made by the spectrum shape and the C/E values in four energy regions. The JENDL-3.2 calculation gives satisfactory prediction except below 0.8 MeV, but that with ENDF/B-VI considerably overestimates the spectrum above 1 MeV. From the observation of the calculated and measured spectra and of the secondary energy distribution spectra (SED) of the (n, 2n) and inelastic scattering in JENDL-3.2 and ENDF/B-VI, the discrepancies in the calculations are probably due to improper SED of the (n, 2n) reaction for that below 0.8 MeV in JENDL-3.2 and that between 0.8 and 6 MeV and SED of inelastic scattering for the secondary neutron energy between 5 and 10 MeV in ENDF/B-VI. Therefore, the (n, 2n) reaction values in JENDL-3.2 library was reduced by 20% and the SED below 0.8 MeV was replaced with that of ENDF/B-VI, and this library reproduced the experiment within about 10% discrepancy over all energy regions.

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Polarized Proton Induced Breakup of 12C at 14 and 16 MeV

Watanabe

Kashimoto

Hane

et al. 1992

Nuclear Data for Science and Technology

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Measurement of double differential neutron emission cross sections for incident neutrons of 14MeV.

Cited by 11 publications

References 1 publication

Measurements of 181Ta(n,2n)180Ta reaction cross-section at the neutron energy of 14.78 MeV

Measurements of 181Ta(n,2n)180Ta reaction cross-section at the neutron energy of 14.78 MeV

Measurement of Leakage Neutron Spectra from a Spherical Pile of Niobium Bombarded with 14MeV Neutrons and Validation of Its Nuclear Data

Polarized Proton Induced Breakup of 12C at 14 and 16 MeV

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