Measurement of Neutron Reaction Cross Sections between 8 and 14 MeV

Mannhart, W.; Schmidt, D.

doi:10.1063/1.1945083

Cited by 16 publications

(12 citation statements)

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“…Particular attention was paid to reproducing the available experimental data for the total cross section and the (n,xn), (n,xp) and (n,xα) channels especially when these lead to radioactive residual nuclei [160]. Figure 27 shows the evaluation compared with data for the 52 C(n,2n) [163-172] and 52 Cr(n,p) [164,169,170,[172][173][174][175][176] reactions and for the production of protons and alphas on natural chromium. The latter are important for the effect of gas production on material damage.…”

Section: Chromiummentioning

confidence: 99%

The joint evaluated fission and fusion nuclear data library, JEFF-3.3

et al. 2020

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The joint evaluated fission and fusion nuclear data library 3.3 is described. New evaluations for neutroninduced interactions with the major actinides 235 U, 238 U and 239 Pu, on 241 Am and 23 Na, 59 Ni, Cr, Cu, Zr, Cd, Hf, W, Au, Pb and Bi are presented. It includes new fission yields, prompt fission neutron spectra and average number of neutrons per fission. In addition, new data for radioactive decay, thermal neutron scattering, gamma-ray emission, neutron activation, delayed neutrons and displacement damage are presented. JEFF-3.3 was complemented by files from the TENDL project. The libraries for photon, proton, deuteron, triton, helion and alpha-particle induced reactions are from TENDL-2017. The demands for uncertainty quantification in modeling led to many new covariance data for the evaluations. A comparison between results from model calculations using the JEFF-3.3 library and those from benchmark experiments for criticality, delayed neutron yields, shielding and decay heat, reveals that JEFF-3.3 performes very well for a wide range of nuclear technology applications, in particular nuclear energy.

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Section: Chromiummentioning

confidence: 99%

The joint evaluated fission and fusion nuclear data library, JEFF-3.3

et al. 2020

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“…The Cu monitor fulfills these requirements and it seems to be well suited for this application. The disadvantage of 1346 keV γ ray line emitted by 64 Cu (very small self-absorption) is its low emission probability [14]. More threshold detector material was used in order to obtain good counting statistics.…”

Section: Neutron Detectorsmentioning

confidence: 99%

“…As shown by Mannhart and Schmidt[14], weak γ ray counting leads to larger errors. Anyway, the 65 Cu(n, 2n)64 Cu reaction was used in combination with the Bonner-type detector in our case.…”

mentioning

confidence: 90%

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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“…The cross sections data for 67 Zn(n,p) 67 Cu [6][7][8][9], 64 Zn(n,2n) 63 Zn [1,3,7,[10][11][12][13], 89 Y(n,γ) 90m Y [4,[14][15][16][17], 89 Y(n,2n) 88 Y [5,7,10,[18][19][20][21][22][23] reactions are available around the neutron energy of 14 MeV. However, there is comparably huge disagreement [1,8,9,17] and ambiguity in the experimental data, which is most probably due to various nuclear parameters like half-life, γ-ray abundances, monitor cross section and types of detectors used.…”

Section: Introductionmentioning

confidence: 99%

Measurement of 67Zn(n,p)67Cu, 64Zn(n,2n)63Zn, 89Y(n,γ)90mY and 89Y(n,2n)88Y reaction cross sections at the neutron energy of 14.54 MeV with covariance analysis

Pasha

Basavanna

Yerranguntla

et al. 2019

J Radioanal Nucl Chem

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The 67 Zn(n,p) 67 Cu, 64 Zn(n,2n) 63 Zn, 89 Y(n,γ) 90m Y and 89 Y(n,2n) 88 Y reaction cross sections relative to the 197 Au(n,2n) 196 Au monitor reaction have been determined at the neutron energy of 14.54 ± 0.002 MeV by using the method of activation and off-line γ-ray spectrometry. The neutron energy used was obtained from the 3 H(d,n) 4 He reaction. The covariance analysis was performed by taking the uncertainties arising in various attributes and the correlations between those attributes. The analyzed results from the present measurement were compared with the literature data and evaluated data of various libraries like ENDF/B-VIII, JEFF-3.3, JENDL-4.0 and ROSFOND-2010 libraries as well as with the calculated values based on TALYS-1.9 code. Keywords 67 Zn(n,p) 67 Cu • 64 Zn(n,2n) 63 Zn, 89 Y(n,γ) 90m Y and 89 Y(n,2n) 88 Y reactions • 3 H(d,n) 4 He reaction neutron • γ-Ray spectrometry • Covariance analysis • TALYS-1.9

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Measurement of Neutron Reaction Cross Sections between 8 and 14 MeV

Cited by 16 publications

References 0 publications

The joint evaluated fission and fusion nuclear data library, JEFF-3.3

The joint evaluated fission and fusion nuclear data library, JEFF-3.3

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

Measurement of 67Zn(n,p)67Cu, 64Zn(n,2n)63Zn, 89Y(n,γ)90mY and 89Y(n,2n)88Y reaction cross sections at the neutron energy of 14.54 MeV with covariance analysis

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Measurement of Neutron Reaction Cross Sections between 8 and 14 MeV

Cited by 16 publications

References 0 publications

The joint evaluated fission and fusion nuclear data library, JEFF-3.3

The joint evaluated fission and fusion nuclear data library, JEFF-3.3

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

Measurement of 67Zn(n,p)67Cu, 64Zn(n,2n)63Zn, 89Y(n,γ)90mY and 89Y(n,2n)88Y reaction cross sections at the neutron energy of 14.54 MeV with covariance analysis

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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