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Program - Brookhaven National Laboratory

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In an effort to maintain the quality of the neutron cross section standards, an IAEA Data Development<br />

Project was initiated to provide a mechanism for allowing new experimental data and improvements in<br />

evaluation procedure to be used in new evaluations of the neutron standards. This Project has broadened<br />

its range of activities beyond that of the traditional activities related to the cross section standards by<br />

including work on extending the energy ranges of the standards and also “reference data” that are not so<br />

widely used as the standards but can be very useful in the measurements of certain types of cross sections.<br />

Ongoing work in this Project has included the following activities: an update of the experimental data to<br />

be used in cross section standards evaluations, testing of the uncertainties obtained in the international<br />

standards evaluation, a study of different smoothing procedures for standards, improvements in the gold<br />

capture cross section at energies below where it is considered a standard but is used in capture cross<br />

section measurements for astrophysical applications, work on reference prompt gamma-ray production<br />

cross sections for fast neutron-induced reactions, and combining measurements of the 235 U thermal neutron<br />

fission spectrum with the evaluation of the 252 Cf spontaneous fission neutron spectrum with the aim of<br />

deriving an improved 235 U thermal neutron fission spectrum. The work done in each of the activities in<br />

this project will be discussed.<br />

BF 3 11:20 AM<br />

New Evaluation of n+ 63,65 Cu Nuclear Cross Section Data up to 200 MeV Neutron Energy<br />

P. Pereslavtsev, A. Konobeyev, U. Fischer<br />

Association KIT-Euratom, Karlsruhe Institute of Technology (KIT), Institut für Neutronenphysik u.<br />

Reaktortechnik, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen Karlsruhe, Germany<br />

Vladimir Sobes, Luiz Leal<br />

Nuclear Data Group and Critical Safety, Oak Ridge <strong>National</strong> <strong>Laboratory</strong>, P.O. Box 2008, Oak Ridge, TN<br />

37831, USA<br />

New high energy neutron cross section data have been evaluated for the stable copper isotopes 63,65 Cu in<br />

the energy range from 1-10 −11 up to 200 MeV. The new evaluation provides a complete and consistent<br />

set of reaction data as required for the nuclear analyses of existing and planned facilities including various<br />

transport, heating, shielding and radiation damage calculations. An automated procedure developed at<br />

KIT for nuclear data evaluations makes use of nuclear model results and different experimental data,<br />

including differential and relevant integral ones. The TALYS-1.4 computer code is used to generate a<br />

full set of nuclear reaction data for neutron energies from 0.001 to 200 MeV. TALYS includes many<br />

nuclear reaction models that increase it flexibility and enables high quality model calculations starting<br />

from keV to intermediate and high neutron energies. The statistical Hauser-Feshbach theory is applied<br />

for the compound nuclear reactions and the two-component exciton model is used for the description<br />

of the pre-equilibrium reactions. The nuclear level densities are calculated within generalized superfluid<br />

model. The optical model calculations are performed with ECIS-06 code implemented in TALYS making<br />

use of default optical model potentials (OMPs) for neutrons and protons, external OMPs for deuterons<br />

and alphas and newly developed OMPs for tritons and helions. New resonance parameters evaluations for<br />

n+ 63,65 Cu including covariance data were done with the SAMMY code. This evaluation is based on the new<br />

measurements performed at GELINA on enriched isotopic copper samples for the capture cross sections<br />

and on old measurements preformed at the Oak Ridge Electron Linear Accelerator (ORELA) on highly<br />

enriched isotopic copper samples for the neutron transmission. The reaction cross sections obtained with<br />

TALYS calculations were compared against available experimental data. Validated reaction cross-section<br />

data from the European Activation File (EAF-2010) were adopted as far as suitable for the evaluation<br />

in the neutron energy range below 20 MeV. The Kalbach systematics was used for the description of the<br />

38

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