Measurement of the<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" display="inline"><mml:mmultiscripts><mml:mi mathvariant="normal">Am</mml:mi><mml:mprescripts /><mml:none /><mml:mrow><mml:mn>241</mml:mn></mml:mrow></mml:mmultiscripts></mml:math><mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" display="inline"><mml:mrow><mml:mo stretchy="false">(</mml:mo><mml:mi>n</mml:mi><mml:mo>,</mml:mo><mml:mn>2</mml:mn><mml:mi>n</mml:mi><mml:mo stretchy="false">)</mml:mo></mml:mrow></mml:math>reaction

Perdikakis, G.; Papadopoulos, C.; Vlastou, R.; Lagoyannis, A.; Spyrou, A.; Kokkoris, M.; Galanopoulos, S.; Patronis, N.; Karamanis, D.; Zarkadas, Ch.; Kalyva, G.; Kossionides, S.

doi:10.1103/physrevc.73.067601

Cited by 13 publications

(13 citation statements)

References 19 publications

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“…Below 14 MeV, we rely on an (n,2n) excitation function shape from our GNASH calculations. Recent data reported by Perdikakis [114] appear contradictory, and were not used in the evaluation. Furthermore, preliminary measurements by a TUNL-LANL-LLNL at the TUNL facility appear to be in good agreement with our evaluation.…”

Section: Thementioning

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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Section: Thementioning

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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“…First, quasi-mono-energetic neutrons with energies of 8.34 and 9.15 MeV were produced via the 2 H(d,n) 3 He reaction (Q = 3.269 MeV) at E d = 5.5 and 6.3 MeV, respectively, using a deuterium gas target. The target cell was 4 cm in length and 4 cm in diameter with a 5-µm molybdenum entrance window.…”

Section: B Irradiation Setupmentioning

confidence: 99%

“…The mean neutron energy and yield distributions as a function of deuteron energy and emission angle for the primary neutrons of the 2 H(d,n) 3 He and 3 H(d,n) 4 He reactions were calculated by the code ENERGYSET [13,14], which is based on the reaction cross-section evaluations of Ref. [15] and energy-loss estimates with stopping powers of Ref.…”

Section: Neutron Energy and Flux Determinationmentioning

confidence: 99%

“…Two references report measured cross sections for the 241 Am(n,2n) reaction at neutron energies around 14 MeV [1,2], and two recent works report data for neutron energies from threshold to 14 MeV [3,4]. At 14 MeV, the data of Refs.…”

Section: Introductionmentioning

confidence: 99%

“…The data of Refs. [3,4] agree well below 10 MeV but reveal huge discrepancies around 11 MeV. Estimates of the cross section available from applications libraries show a large spread in the predicted excitation function [5][6][7] (see Fig.…”

Section: Introductionmentioning

confidence: 99%

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High resolution measurements of theAm241(n,2n
Sage
¹
,
Semkova
²
,
Bouland
³

et al. 2010
Phys. Rev. C
26
0
11
0
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Measurements of the 241 Am(n,2n) reaction cross section have been performed at the Joint Research Centre (JRC) Geel in the frame of a collaboration between the European Commission (EC) JRC and French laboratories from CNRS and the Commissariatà L'Energie Atomique (CEA) Cadarache. Raw material coming from the Atalante facility of CEA Marcoule has been transformed by JRC Karlsruhe into suitable 241 AmO 2 samples embedded in Al 2 O 3 matrices specifically designed for these measurements. The irradiations were carried out at the 7-MV Van de Graaff accelerator. The 241 Am(n,2n) reaction cross section was determined relative to the 27 Al(n,α) 24 Na standard cross section. The measurements were performed in four sessions, using quasi-monoenergetic neutrons with energies ranging from 8 to 21 MeV produced via the 2 H(d,n) 3 He and the 3 H(d,n) 4 He reactions. The induced activity was measured by standard γ -ray spectrometry using a high-purity germanium detector. Below 15 MeV, the present results are in agreement with data obtained earlier. Above 15 MeV, these measurements allowed the experimental investigation of the 241 Am(n,2n) reaction cross section for the first time. The present data are in good agreement with predictions obtained with the TALYS code that uses an optical and fission model developed at CEA.

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Nuclear Data Sheets for A = 240

Singh

Browne

2008

Nuclear Data Sheets

View full text Add to dashboard Cite

Measurement of theAm241(n,2n)reaction

Cited by 13 publications

References 19 publications

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

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

High resolution measurements of theAm241(n,2n
Sage
¹
,
Semkova
²
,
Bouland
³

et al. 2010
Phys. Rev. C
26
0
11
0
View full text Add to dashboard Cite

Nuclear Data Sheets for A = 240

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Measurement of theAm241(n,2n)reaction

Cited by 13 publications

References 19 publications

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

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

High resolution measurements of theAm241(n,2nSage1, Semkova2, Bouland3 et al. 2010Phys. Rev. C260110View full textAdd to dashboardCite

Nuclear Data Sheets for A = 240

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Product

Resources

About

High resolution measurements of theAm241(n,2n
Sage
¹
,
Semkova
²
,
Bouland
³

et al. 2010
Phys. Rev. C
26
0
11
0
View full text Add to dashboard Cite