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RISS 인기검색어
- 검색키워드
- 저자 : Pronyaev, V. G. (검색결과 3 건)
- 무료
- 기관 내 무료
- 유료
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An Update of the Nuclear Data Standards Activities
Allan D. Carlson,Vladimir G. Pronyaev,Franz-Josef Hambsch,Franz Kappeler,Wolf Mannhart,Alberto Mengoni,Ronald O. Nelson,Patrick Talou,Siegfried Tagesen 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
To allow new experimental data and improvements in evaluation procedure to be used in a timely manner in producing standards evaluations, an IAEA Data Development Project was initiated. For this project, it was decided that, in addition to the traditional activities related to standards, studies should be done on the possibility of extending the energy ranges of the standards and whether to include "reference data" that are not as well known as the standards but can be very useful in the measurements of certain types of cross sections. Activities include; an update of the experimental database for the traditional standards; improvements in smoothing procedures for capture cross sections, a review of the status of ^(252)Cf spontaneous fission neutron spectrum measurements; new work on the ^(235)U thermal neutron induced fission neutron spectrum that is not a standard but is important for reactor applications; improved calculations for fission neutron spectra; consideration of the ^(197)Au capture reaction as a reference cross section for capture cross-section measurements at energies of importance to astrophysics; and a study of reference cross sections for prompt gammaray production in fast neutron-induced reactions. A review of the progress made by this project will be given.
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Advanced Evaluation of ^(237)Np and ^(243)Am Neutron Data
V. M. Maslov,N. A. Tetereva,V. G. Pronyaev,T. Granier,F.-J. Hambsch 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
The diverse measured data base of n+^(237)Np is evaluated using a generalized least squares code and statistical theory of nuclear reactions. Consistent description of the total, fission and partial inelastic scattering data in 1 - 3 MeV energy range provides an important constraint for the absorption cross section. Important constraints for the measured capture cross section come from the average radiation S0 and S1 strength functions. An abrupt change of the inelastic data shape at En ∼ 1.5 MeV is explained by the sharp increase of the level density of the residual odd-even nuclide ^(237)Np due to the onset of three-quasi-particle excitations. The in fluence of exclusive (n, xnf) pre-fission neutrons on prompt fission neutron spectra and (n, xn) reactions spectra is modeled. Contributions of emissive/non-emissive fission and exclusive spectra of (n, xnf) reactions are defined by a consistent description of the ^(237)Np(n, F), ^(237)Np (n, 2n)^(236s)Np reactions and the ratio of the yields of short-lived isomer (1^-) and long-lived ground (6^-) ^(236)Np states measured at ∼14 MeV. The isomer ratio of the yields of short-lived ground (1^-) ^(242g)Am and long-lived isomer (5^-) ^(242m)Am states in ^(243)Am(n, 2n) reaction is calculated modeling the gamma-decay of the possible Gallaher-Moshkowski doublet states of ^(242) Am.
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Sirakov, I.,Capote, R.,Gritzay, O.,Kim, H. I.,Kopecky, S.,Kos, B.,Paradela, C.,Pronyaev, V. G.,Schillebeeckx, P.,Trkov, A. Springer 2017 European Physical Journal A Vol.53 No.10
<P>Cross sections for neutron interactions with U-238 in the energy region from 5 keV to 150 keV have been evaluated. Average total and capture cross sections have been derived from a least squares analysis using experimental data reported in the literature. The resulting cross sections have been parameterised in terms of average resonance parameters maintaining full consistency with results of optical model calculations by using a dispersive coupled channel optical model potential. The average compound partial cross sections have been expressed in terms of transmission coefficients by applying the Hauser-Feshbach statistical reaction theory including width-fluctuations. A generalized single-level representation compatible with the energy-dependent options of the ENDF-6 format has been applied using standard boundary conditions. The results have been transferred into a full ENDF-6 compatible data file.</P>
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