Untersuchung von (n, 2n) anregungsfunktionen

Bormann, M.; Behrend, A.; Riehle, I.; Vogel, Oliver

doi:10.1016/0375-9474(68)90006-7

Cited by 125 publications

(12 citation statements)

References 18 publications

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“…The results of Bormann et al [26] are in agreement with the present data. The attenuation of the incident neutrons and self absorption of the emitted gamma-rays represented a very small correction.…”

Section: Sn(n 2n) 111 Sn Reactionsupporting

confidence: 96%

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Activation cross sections for reactions induced by 14 MeV neutrons on natural tin and enriched¹¹²Sn targets with reference to¹¹¹In productionviaradioisotope generator¹¹²Sn(n, 2n)¹¹¹Sn →¹¹¹In

Běták¹,

Mikołajczak²,

Staniszewska³

et al. 2005

Radiochimica Acta

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Activation cross sections / Ge detector / Neutron-induced reactions / γ -ray spectroscopy / Tin region / Neutron generatorSummary. We measured activation cross sections via γ -ray spectroscopy using high-purity germanium detectors for 16 reactions induced by (14.4 ± 0.2) MeV neutrons on isotopes of tin. The cross sections are: σ( 112 Sn(n, 2n) 111 Sn) = (1104 ± 43) mb, σ( 112 Sn(n, p) 112m In) = (33.6 ± 2.1) mb, σ( 112 Sn(n, p) 112g In) = (42.7 ± 3.1) mb, σ( 114 Sn(n, 2n) 113 Sn) = (1270 ± 115) mb, σ( 114 Sn(n, p) 114m2 In) = (20.5 ± 1.1) mb, σ( 115 Sn(n, p) 115m In) = (35.2 ± 2.6) mb, σ( 116 Sn(n, p) 116m2 In) = (11.1 ± 0.5) mb, σ( 117 Sn(n, n p) 116m2 In) = (1.35 ± 0.11) mb, σ( 117 Sn(n, p) 117m In) = (4.5 ± 0.4) mb, σ( 117 Sn(n, p) 117g In) = (12.8 ± 0.7) mb, σ( 117 Sn(n, n ) 117m Sn) = (246 ± 21) mb, σ( 118 Sn(n, 2n) 117m Sn) = (816 ± 70) mb, σ( 118 Sn(n, α) 115g Cd) = (1.26 ± 0.16) mb, σ( 120 Sn(n, α) 117m Cd) = (0.27 ± 0.04) mb, σ( 120 Sn(n, α) 117g Cd) = (0.29 ± 0.06) mb and σ( 124 Sn(n, 2n) 123m Sn) = (590 ± 26) mb.Two 112 Sn targets enriched to 62.5% and 84%, respectively, were used for these measurements in addition to the natural tin. The cross sections were compared with experimental data found in the literature, with published empirical formulae and with model calculations including also the pre-equilibrium contribution. For reactions which do not involve protons from below the closed Z = 50 shell, the agreement to the data is reasonable, it is somewhat weaker for the (n, p) reactions and still worse in the case of (n, α), where, however, the pre-equilibrium component is not described properly by the models included so far. The possibility of production of 111 Sn → 111 In generator system is considered.

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Section: Sn(n 2n) 111 Sn Reactionsupporting

confidence: 96%

“…Estimated cross section of the [(n, pn) + (n, d) + (n, n p)] reaction obtained using formula of Ref. [26] is ca. 170 mb.…”

Section: Sn(n 2n) 111 Sn Reactionmentioning

confidence: 99%

Activation cross sections for reactions induced by 14 MeV neutrons on natural tin and enriched¹¹²Sn targets with reference to¹¹¹In productionviaradioisotope generator¹¹²Sn(n, 2n)¹¹¹Sn →¹¹¹In

Běták¹,

Mikołajczak²,

Staniszewska³

et al. 2005

Radiochimica Acta

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“…3 a-d. There is a good agreement with experimental [38,39] and evaluated data [37]. Deviations from experimental data are observed only for Ni-isotopes [-37, 40, 41] where the calculations predict (several times) too high values for E,> 16MeV.…”

Section: Results and Conclusionsupporting

confidence: 70%

Description of (n, p) and (n, 2n-activation cross sections for medium-mass nuclei within statistical multistep theory

Kalka

Torjman

Lien

et al. 1990

Z. Physik A - Atomic Nuclei

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“…On the other hand, the other experimental data measured in last 20 years give a relatively lower cross section, about 1.5 b. ENDF/B-VII.1 seems to follow the experimental data by Kasugai who presented the smallest cross section around 14 MeV. We determine in the present evaluation to follow the data points measured by Bormann [46], Murahira, and Sakane on the whole. Above 16 MeV, the present calculation shows almost the same cross section as ENDF/B-VII.1.…”

Section: (N 2n) Reaction Cross Sectionsupporting

confidence: 76%

Evaluation of neutron nuclear data of praseodymium-141 and -143

Minato

2013

Journal of Nuclear Science and Technology

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For the next version of JENDL general purpose file, neutron nuclear data on 141,143 Pr are evaluated considering cross sections and spectra provided from experiments in the fast neutron energy region up to 20 MeV. Total and elastic cross sections are derived from optical model. Pre-equilibrium and direct-reaction processes are taken into account in addition to the compound process. The statistical model is applied to calculate the cross sections above the resolved resonance region. For unstable 143 Pr nuclide having less experimental data, we use the same parameters as 141 Pr for mass-dependent and -independent terms in the optical potential. The resolved resonance parameter remains unchanged from JENDL-4.0. The present evaluations give consistent results with experimental data, reflecting newly measured one. The evaluated data are compiled in ENDF-6 format for the next version of JENDL.Keywords: evaluation; neutron nuclear data; cross section; spectrum; fission product; praseodymium-141; praseodymium-143 IntroductionThe fourth version of the Japanese Evaluated Nuclear Data Library (JENDL-4.0 [1]) was released in May 2010. In the library, 215 nuclides are regarded as fission products in the region from Z = 30 to 68. The resolved and unresolved resonance parameters for all of those nuclides were examined by reviewing experimental data; however, the fast neutron region above the resolved resonances was re-evaluated only for 174 nuclides. The remaining 41 nuclides, which were not examined for the release of JENDL-4.0, need to be re-evaluated for the next version of JENDL general purpose file.Praseodymium-141 and -143, which are the target isotopes of the present work, are included in the remaining 41 nuclides. As mentioned, the resolved resonance parameters were re-examined in JENDL-4.0; however, cross sections in the fast neutron region were not revised. The last update was performed in JENDL-3.2 released at 1994, and the calculation was performed by the statistical-model code CASTHY [2] with the competing reaction using PEGASUS [3]. Several experimental data measured after the release of JENDL-3.2, which show a different value from old one referred by JENDL-4.0 (i.e., −3.2), also inclines us re-evaluation. The purpose of this study is to improve the nuclear data in the fast neutron

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Untersuchung von (n, 2n) anregungsfunktionen

Cited by 125 publications

References 18 publications

Activation cross sections for reactions induced by 14 MeV neutrons on natural tin and enriched¹¹²Sn targets with reference to¹¹¹In productionviaradioisotope generator¹¹²Sn(n, 2n)¹¹¹Sn →¹¹¹In

Activation cross sections for reactions induced by 14 MeV neutrons on natural tin and enriched¹¹²Sn targets with reference to¹¹¹In productionviaradioisotope generator¹¹²Sn(n, 2n)¹¹¹Sn →¹¹¹In

Description of (n, p) and (n, 2n-activation cross sections for medium-mass nuclei within statistical multistep theory

Evaluation of neutron nuclear data of praseodymium-141 and -143

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Untersuchung von (n, 2n) anregungsfunktionen

Cited by 125 publications

References 18 publications

Activation cross sections for reactions induced by 14 MeV neutrons on natural tin and enriched112Sn targets with reference to111In productionviaradioisotope generator112Sn(n, 2n)111Sn →111In

Activation cross sections for reactions induced by 14 MeV neutrons on natural tin and enriched112Sn targets with reference to111In productionviaradioisotope generator112Sn(n, 2n)111Sn →111In

Description of (n, p) and (n, 2n-activation cross sections for medium-mass nuclei within statistical multistep theory

Evaluation of neutron nuclear data of praseodymium-141 and -143

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Activation cross sections for reactions induced by 14 MeV neutrons on natural tin and enriched¹¹²Sn targets with reference to¹¹¹In productionviaradioisotope generator¹¹²Sn(n, 2n)¹¹¹Sn →¹¹¹In

Activation cross sections for reactions induced by 14 MeV neutrons on natural tin and enriched¹¹²Sn targets with reference to¹¹¹In productionviaradioisotope generator¹¹²Sn(n, 2n)¹¹¹Sn →¹¹¹In