ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data

Chadwick, M.B.; Herman, M.; Obložinský, P.; Dunn, Michael E.; Danon, Y.; Kahler, Albert C.; Smith, Donald L.; Pritychenko, B.; Arbanas, Goran; Arcilla, R.; Brewer, R.W.; Brown, David; Capote, R.; Carlson, A.D.; Cho, Y.S.; Derrien, H.; Guber, K. H.; Hale, Gerald M.; Hoblit, S.; Holloway, Shannon T.; Johnson, Timothy D.; Kawano, Toshihiko; Kiedrowski, Brian C.; Kim, H.; Kunieda, Satoshi; Larson, N. M.; Leal, L.C.; Lestone, J. P.; Little, Robert C.; McCutchan, E. A.; MacFarlane, R.E.; MacInnes, Mark A.; Mattoon, Caleb; McKnight, R.D.; Mughabghab, S.F.; Nobre, G. P. A.; Palmiotti, G.; Palumbo, A.; Pigni, Marco T.; Pronyaev, V.G.; Sayer, R.O.; Sonzogni, A. A.; Summers, N. C.; Talou, P.; Thompson, I. J.; Trkov, A.; Vogt, R.; Marck, S. C. van der; Wallner, A.; White, Morgan Curtis; Wiarda, Dorothea; Young, P.G.

doi:10.1016/j.nds.2011.11.002

Cited by 2,278 publications

(1,301 citation statements)

References 184 publications

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“…The comparison of the present results with the most recent evaluation of the fission cross-section of 241 Am from the ENDF/B-VII.1 data library [27,28] in fig. 3 shows good agreement over the entire energy range.…”

Section: Evaluated Data and Empire Calculationsmentioning

confidence: 72%

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Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF

et al. 2013

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Abstract. The neutron-induced fission cross-section of 241 Am has been measured relative to the standard fission cross-section of 235 U between 0.5 and 20 MeV. The experiment was performed at the CERN n TOF facility. Fission fragments were detected by a fast ionization chamber by discriminating against the α-particles from the high radioactivity of the samples. The high instantaneous neutron flux and the low background of the n TOF facility enabled us to obtain uncertainties of ≈ 5%. With the present results it was possible to resolve discrepancies between previous data sets and to confirm current evaluations, thus providing important information for design studies of future reactors with improved fuel burn-up.

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Section: Evaluated Data and Empire Calculationsmentioning

confidence: 72%

“…Comparison of the present cross-section results (full squares) with the most recent ENDF/B-VII.1 evaluation [27] and with a calculation using the EMPIRE code [29]. have been presented in the study of the fission crosssection of 243 Am [23].…”

Section: Figmentioning

confidence: 99%

Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF

et al. 2013

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“…The cross sections evaluated in Ref. [5] are also plotted by the open triangles together with the cross section from the evaluated nuclear data library ENDF/B-VII.1 [6] shown by the dashed line. The evaluated cross sections are very close to the present data for the 7 Be g.s.…”

Section: Discussionmentioning

confidence: 99%

The First Measurement of Cross Section for the ⁷Be(n, α)⁴He Reaction at the Cosmological Energy

Takeda¹,

Kawabata²,

Furono³

et al. 2017

Proceedings of the 14th International Symposium on Nuclei in the Cosmos (NIC2016)

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The cross section for the 4 He(α,n) 7 Be reaction was measured at low energies between E α = 38.50 and 39.64 MeV to solve the cosmological lithium problem. On the basis of the detailed balance principle, the cross section for the 7 Be(n,α) 4 He reaction was obtained at E c.m. = 0.20-0.81 MeV close to the Big Bang nucleosynthesis (BBN) energy window for the first time. The obtained cross sections are significantly smaller than the theoretical estimation used in the BBN calculations. The present results suggest the 7 Be(n,α) 4 He reaction rate is not large enough to solve the cosmological lithium problem.

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“…In addition, we have not yet begun testing in the ZPR, TRIGA and KAPL benchmarks which were essential to the testing in the ENDF/B-VII.1 evaluations [1]. We anticipate finalizing the evaluations in the summer of 2013.…”

Section: Discussionmentioning

confidence: 99%

“…90 Zr: Revised for ENDF/B-VII.1 [1] 91 Zr: Revised for ENDF/B-VII.1 [1] 92 Zr: JENDL-4.0 [3] 93 Zr: WPEC-SG23 and Atlas of Neutron Resonances [2] 94 Zr: WPEC-SG23 and Atlas of Neutron Resonances [2] 95 Zr: JENDL-4.0 [3] (background must be corrected) given by the optical model, so must be subtracted ✴(n,comp-el)…”

Section: The Resonance Regionmentioning

confidence: 99%

Zirconium Evaluations for ENDF/B-VII.2 for the Fast Region

Brown

Arcilla

Capote

et al. 2014

Nuclear Data Sheets

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We have performed a new combined set of evaluations for 90−96 Zr, including new resolved resonance parameterizations from Said Mughabghab for 90,91,92,94,96 Zr and fast region calculations made with EMPIRE-3.1. Because 90 Zr is a magic nucleus, 90 Zr is nearly spherical. Therefore, all even-even nuclei in the evaluation set were evaluated using EMPIRE's OPTMAN coupled channels code and a new soft-rotor optical model potential. This then led to improved (n,el) angular distributions, helping to resolve improper leakage in the older ENDF/B-VII.1β evaluation in KAPL proprietary, ZPR and TRIGA benchmarks. Another consequence of 90 Zr being a magic nucleus is that the level densities in both 90 Zr and 91 Zr are unusually low causing the (n,el) and (n,tot) cross sections to exhibit large fluctuations above the resolved resonance region. To accomodate these fluctuations, we performed a simultaneous constrained generalized least-square fit to (n,tot) for all isotopic and elemental Zr data in EXFOR, using EMPIRE's TOTRED scaling factor. TOTRED rescales reaction cross sections so that the optical model calculations are unaltered by the rescaling and the correct competition between channels is maintained. In this fit, all (n,tot) data in EXFOR was used for Ein > 100 keV, provided the target isotopic makeup could be correctly understood, including spectrum averaged data and data with broad energy resolution. As a result of our fitting procedure, we have full cross material and cross reaction covariance for all Zr isotopes and reactions.

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ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data

Cited by 2,278 publications

References 184 publications

Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF

Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF

The First Measurement of Cross Section for the ⁷Be(n, α)⁴He Reaction at the Cosmological Energy

Zirconium Evaluations for ENDF/B-VII.2 for the Fast Region

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ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data

Cited by 2,278 publications

References 184 publications

Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF

Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF

The First Measurement of Cross Section for the 7Be(n, α)4He Reaction at the Cosmological Energy

Zirconium Evaluations for ENDF/B-VII.2 for the Fast Region

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Product

Resources

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The First Measurement of Cross Section for the ⁷Be(n, α)⁴He Reaction at the Cosmological Energy