239Pu and 241Am (n, 2n) cross-section measurements near E
 n = 14 MeV

Lougheed, R. W.; Webster, W.M.; Namboodiri, M.N.; Nethaway, D.R.; Moody, K. J.; Landrum, J.H.; Hoff, R. W.; Dupzyk, R.J.; McQuaid, J.H.; Gunnink, R.; Watkins, E. D.

doi:10.1524/ract.2002.90.12_2002.833

Cited by 23 publications

(12 citation statements)

References 8 publications

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“…The TUNL results are compared with previous measurements reported by Gancarz [3], Filatenkov et al [4], and Lougheed et al [5] near 14 MeV and the recent data by Perdikakis et al at lower energies [7]. The data agree within the reported errors in the 14-MeV energy region.…”

Section: Discussionsupporting

confidence: 79%

“…Indeed, initially, before the older 14 MeV (n, 2n) measurements of Lougheed et al [5] and Gancarz et al [3] were made available to us, the calculated predictions for this cross section were poor. For example, the old ENDF/B-VI evaluation was discrepant with the best measurements by ∼50%.…”

Section: Nuclear-model Calculationsmentioning

confidence: 97%

“…Most of the previous data were obtained at neutron energies around 14 MeV [3][4][5]. Recent evaluations show a large spread in the predicted cross section for this reaction [6].…”

Section: Introductionmentioning

confidence: 99%

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Measurement of theAm241(n,2n) reaction cross section from 7.6 MeV to 14.5 MeV

Tonchev¹,

Angell²,

Boswell³

et al. 2008

Phys. Rev. C

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The (n, 2n) cross section of the radioactive isotope 241 Am (T 1/2 = 432.6 y) has been measured in the incident neutron energy range from 7.6 to 14.5 MeV in steps of a few MeV using the activation technique. Monoenergetic neutron beams were produced via the 2 H(d, n) 3 He reaction by bombarding a pressurized deuterium gas cell with an energetic deuteron beam at the TUNL 10-MV Van de Graaff accelerator facility. The induced γ -ray activity of 240 Am was measured with high-resolution HPGe detectors. The cross section was determined relative to Al, Ni, and Au neutron activation monitor foils, measured in the same geometry. Good agreement is obtained with previous measurements at around 9 and 14 MeV, whereas for a large discrepancy is observed when our data are compared to those reported by Perdikakis et al. near 11 MeV. Very good agreement is found with the END-B/VII evaluation, whereas the JENDL-3.3 evaluation is in fair agreement with our data.

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Section: Discussionsupporting

confidence: 79%

Section: Nuclear-model Calculationsmentioning

confidence: 97%

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Measurement of theAm241(n,2n) reaction cross section from 7.6 MeV to 14.5 MeV

Tonchev¹,

Angell²,

Boswell³

et al. 2008

Phys. Rev. C

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“…Prior to this work, precision activation measurements had been made near 14 MeV by Lougheed et al [96]. Other measurements based on measuring the two secondary neutrons by Frehaut and by Mather were thought to be problematic -Mather's being unrealistically high near threshold, and Frehaut's being unrealistically low -and were therefore discounted in the evaluation.…”

mentioning

confidence: 99%

“…33, and adopted for ENDF/B-VII.0. Pu(n, 2n) cross section compared with data, and with previous evaluations.The evaluation was based upon the GEANIE-GNASH data and the Lougheed 14 MeV data [96]. The ENDF/B-VII.0 evaluation (red line) is also refered to as the "GEANIE-project" evaluation.…”

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confidence: 99%

ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

Chadwick

Obložinský

Herman

et al. 2006

Nuclear Data Sheets

1,963

908

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We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, released by the U.S. Cross Section Evaluation Working Group (CSEWG) in December 2006, contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes. The new evaluations are based on both experimental data and nuclear reaction theory predictions.The principal advances over the previous ENDF/B-VI library are the following: (1) New cross sections for U, Pu, Th, Np and Am actinide isotopes, with improved performance in integral validation criticality and neutron transmission benchmark tests; (2) More precise standard cross sections for neutron reactions on H, 6 Li, 10 B, Au and for 235,238 U fission, developed by a collaboration with the IAEA and the OECD/NEA Working Party on Evaluation Cooperation (WPEC); (3) Improved thermal neutron scattering; (4) An extensive set of neutron cross sections on fission products developed through a WPEC collaboration; (5) A large suite of photonuclear reactions; (6) Extension of many neutron-and proton-induced reactions up to an energy of 150 MeV; (7) Many new light nucleus neutron and proton reactions; (8) Post-fission beta-delayed photon decay spectra; (9) New radioactive decay data; and (10) New methods developed to provide uncertainties and covariances, together with covariance evaluations for some sample cases.The paper provides an overview of this library, consisting of 14 sublibraries in the same, ENDF-6 format, as the earlier ENDF/B-VI library. We describe each of the 14 sublibraries, focusing on neutron reactions. Extensive validation, using radiation transport codes to simulate measured critical assemblies, show major improvements: (a) The long-standing underprediction of low enriched U thermal assemblies is removed; (b) The 238 U, 208 Pb, and 9 Be reflector biases in fast systems are largely removed; (c) ENDF/B-VI.8 good agreement for simulations of highly enriched uranium assemblies is preserved; (d) The underprediction of fast criticality of 233,235 U and 239 Pu assemblies is removed; and (e) The intermediate spectrum critical assemblies are predicted more accurately.We anticipate that the new library will play an important role in nuclear technology applications, including transport simulations supporting national security, nonproliferation, advanced reactor and fuel cycle concepts, criticality safety, medicine, space applications, nuclear astrophysics, and nuclear physics facility design. The ENDF/B-VII.0 library is archived at the National Nuclear Data Center,

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