Reaction mechanism and shell effects from the interaction of 14.6 MeV neutrons with nuclei

Strohal, P.; Cindro, N.; Eman, B.

doi:10.1016/0029-5582(62)90031-7

Cited by 110 publications

(11 citation statements)

References 45 publications

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“…48 together with TENDL-2017 evaluation except for the two 14-MeV data points of Refs. [160,161] which exceed essentially all other equivalent data. Results of Ref.…”

Section: Momentioning

confidence: 63%

Recommended nuclear data for medical radioisotope production: diagnostic gamma emitters

Tárkányi

Ignatyuk

Hermanne

et al. 2018

J Radioanal Nucl Chem

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An extensive series of evaluations have been performed as part of an IAEA coordinated research project to study a set of nuclear reactions that produce the diagnostic gamma-ray emitting radionuclides 51 Cr, 99m Tc, 111 In, 123 I and 201 Tl. Recommended cross-section data in the form of excitation functions have been derived, along with quantifications of their uncertainties. These evaluations involved the compilation of all previously published values and newly measured experimental data, followed by critical assessments and selection of those experimental datasets and accompanying uncertainties judged to be fully valid and statistically consistent for model-independent least-squares fitting by means of Padé approximations. Integral yields as a function of the energy were also calculated on the basis of the recommended cross sections deduced from these various fits. All evaluated numerical results and their corresponding uncertainties are available online at www-nds.iaea.org/medical/gamma_emitters.html and also on the medical portal of the International Atomic Energy Agency/Nuclear Data Section (IAEA-NDS) www-nds.iaea.org/medportal/.

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“…48 together with TENDL-2017 evaluation except for the two 14-MeV data points of Refs. [160,161] which exceed essentially all other equivalent data. Results of Ref.…”

Section: Momentioning

confidence: 63%

Recommended nuclear data for medical radioisotope production: diagnostic gamma emitters

Tárkányi

Ignatyuk

Hermanne

et al. 2018

J Radioanal Nucl Chem

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“…Additionally, after normalization for the gamma-yield per decay of the 1368.626 keV gamma line of 24 Na, the reported data of Ref. [122] changed by 12%. Refrences [92,131] adopted the 63 Cu(n, 2n) 62 Cu reaction as the monitor reaction.…”

Section: Mo Reactionmentioning

confidence: 98%

“…Upon normalization with the IRDFF-II evaluation of the 56 Fe(n, p) 56 Mn reaction, the cross sections changed by 16% and 9%, respectively. Refrences [56,94,[120][121][122][123][124][125][126][127][128][129][130] adopted the 27 Al(n, α) 24 Na reaction as the monitor reaction. After normalization with the IRDFF-II evaluation of the 27 Al(n, α) 24 Na reaction, the cross sections changed by 7% for Refs.…”

Section: Mo Reactionmentioning

confidence: 99%

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14.77 MeV neutron-induced nuclear reaction cross sections for zinc, yttrium, and molybdenum targets*

et al. 2023

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The cross sections for neutron-induced nuclear reactions on natural zinc, yttrium and molybdenum targets were measured at 14.77 ± 0.17 MeV neutron energy by the activation technique, offline gamma-ray spectrometry along with a detailed covariance analysis. The uncertainty in statistical model calculations of cross sections for (n,2n), (n,p), (n,α) and (n,γ) reactions for natural zinc, yttrium and molybdenum from 13 to 17 MeV neutron energy was calculated with the TALYS-1.96 nuclear code. The measured cross sections of the present study are compared with experimental cross sections reported in the EXFOR database, cross sections calculated with the TALYS-1.96 and EMPIRE-3.2.3 nuclear codes and evaluated nuclear data from the TENDL-2019, JENDL-5 and ENDF/B-VIII.0 libraries.

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“…Figure 2 shows that the experimentally measured 97 Mo(n,p) 97 Nb reaction cross section at the effective neutron energy of 14.54 ± 0.24 MeV is in good agreement with the evaluated data of ENDF/B-VIII.0 [19], JEFF-3.3 [20], JENDL-4.0 [21], ROSFOND-2010 [22] and CENDL-3.1 [23] libraries, literature data [25, 27, 29-32, 35-37, 42, 43] as well as with the value from TALYS-1.9 [7].However, A large variation was found among the data of Paul et al [39], Strohalet al [40] and Tikkuet al [41] compared to the experimental data of others [25, 27, 29-32, 35-37, 42, 43] and present work as well as from the theoretically estimated values of TALYS-1.9 and evaluated data of different libraries.…”

Section: Estimation Ofmentioning

confidence: 99%

Measurement of 92Mo(n,α)89Zr, 97Mo(n,p)97Nb, 148Nd(n,2n)147Nd and 146Nd(n,p)146Pr reaction cross sections at the neutron energy of 14.54 MeV with covariance analysis

Sunitha

Suryanarayana

Nagaraja

et al. 2020

J Radioanal Nucl Chem

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The 92 Mo(n,α) 89 Zr, 97 Mo(n,p) 97 Nb, 148 Nd(n,2n) 147 Nd and 146 Nd(n,p) 146 Pr reaction cross sections with the neutron of energy of 14.54 ± 0.24 MeV have been measured by using the method of activation and off-line γ-ray spectrometry. The neutron was generated from the D-T reaction at the PURNIMA neutron generator of BARC. The 197 Au(n,2n) 196 Au monitor reaction was used for the estimation of neutron flux. The covariance analysis for the uncertainties of the cross sections has been carried out by considering the partial uncertainties of different attributes. The present data have been compared with the literature data, evaluated data and theoretically calculated values from TALYS-1.9 code. Keywords 92 Mo(n,α) 89 Zr, 97 Mo(n,p) 97 Nb, 148 Nd(n,2n) 147 Nd and 146 Nd(n,p) 146 Pr reaction cross sections • Activation and offline γ-ray spectrometry • Covariance analysis

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Reaction mechanism and shell effects from the interaction of 14.6 MeV neutrons with nuclei

Cited by 110 publications

References 45 publications

Recommended nuclear data for medical radioisotope production: diagnostic gamma emitters

Recommended nuclear data for medical radioisotope production: diagnostic gamma emitters

14.77 MeV neutron-induced nuclear reaction cross sections for zinc, yttrium, and molybdenum targets*

Measurement of 92Mo(n,α)89Zr, 97Mo(n,p)97Nb, 148Nd(n,2n)147Nd and 146Nd(n,p)146Pr reaction cross sections at the neutron energy of 14.54 MeV with covariance analysis

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