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Program - Brookhaven National Laboratory

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Advances in Reactor Physics Linking Research, Industry, and Education, Knoxville, TN, April 15 20,<br />

2012. [3] N. M. Larson, Updated Users’ Guide for SAMMY: Multilevel R-Matrix Fits to Neutron Data Using<br />

Bayes’ Equations, Report ENDF-364 and ORNL/TM-9179/R6, Oak Ridge <strong>National</strong> <strong>Laboratory</strong>, Oak<br />

Ridge, TN (May 2003). Also report ORNL/TM-9179/R7 (2006). [4] M. B. Chadwick et al., “ENDF/B-<br />

VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and<br />

Decay Data,” Nuclear Data Sheets, 112, 2887 (2011). [5] S. F. Mughabghab, Atlas of Neutron Resonances:<br />

Thermal Cross Sections and Resonance Parameters, Elsevier Publisher, Amsterdam (2006). [6] Neutron<br />

Scattering Lengths found at http://www.ati.ac.at/ ∼ neutropt/scattering/table.html. [7] A. Trkov<br />

et al., “Covariances of Evaluated Nuclear Cross Section Data for 232 Th, 180,182,183,184,186 W and 55 Mn,”<br />

Nuclear Data Sheets, 112, 3098 (2011). [8] P. Batistoni et al., “Neutronics Benchmark Experiment on<br />

Tungsten,” J. Nucl. Materials, 329 333, 683 (2004). [9] ICSBEP 2006, International Handbook of Evaluated<br />

Criticality Safety Benchmark Experiments, Technical Report NEA/NSC/DOC(95)03, NEA Nuclear<br />

Science Committee, Nuclear Energy Agency, OECD 2006, Paris, France.<br />

Session CA Neutron Resonances<br />

Monday March 4, 2013<br />

Room: Met East at 1:30 PM<br />

CA 1 1:30 PM<br />

Evaluation of Neutron Resonance Cross Section Data at GELINA<br />

Peter Schillebeeck, Bjorn Becker, Federica Emiliani, Jan Heyse, Kim Kauwenbergs, Stefan Kopecky,<br />

Willy Mondelaers, Arjan Plompen, Peter Siegler, Konstantin Volev<br />

EC - JRC - IRMM, Retieseweg 111, B - 2440 Geel, Belgium<br />

Vladimir Pronayev<br />

IPPE, Obninsk, Russia<br />

Ivan Sirakov<br />

INRNE, Sofia, Bulgaria<br />

Cristian Massimi<br />

INFN Bologna, Italy<br />

Over the last decade, the EC - JRC - IRMM, in collaboration with other institutes such as INRNE Sofia,<br />

INFN Bologna, IPPE Obninsk and ORNL, has made an intense effort to improve the quality of neutroninduced<br />

cross section data in the resonance region. These improvements relate to both the infrastructure<br />

of the facility and the measurement, data reduction and analysis procedures. As a result total and reaction<br />

cross section data in the resonance region with uncertainties better than 0.5% and 2%, respectively, can<br />

be produced together with evaluated data files for both the resolved and unresolved resonance region.<br />

A special format has been developed to provide the experimental data with full covariance information.<br />

The format is very convenient to account for all uncertainty components whilst avoiding bias effects when<br />

model parameters are determined by least squares adjustment of experimental data. The methodology to<br />

produce full ENDF compatible files, including covariances, will be illustrated by the production of resolved<br />

resonance parameter files for Cd and W and an evaluation for 197 Au in the unresolved resonance region.<br />

The latter, which is part of a project to improve the 197 Au(n,γ) cross section standard, will be explained<br />

in detail, starting from the data reduction up to a parameterization of averaged cross section data based<br />

on the R-matrix formalism combined with level statistical model distributions.<br />

40

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