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Program - Brookhaven National Laboratory

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Neutron elastic scattering, radiative capture and fission cross section covariances for Np-237 are evaluated<br />

in the resolved resonance region. Analytical expressions describing the sensitivities of cross sections with<br />

respect to the resonance parameters at certain energy point are derived from the Multi-level Breit-Wigner<br />

formula. Then they are numerically integrated to obtain the sensitivities of average cross sections to<br />

the resonance parameters in an arbitrary energy bin. The full covariance matrix is constructed with a<br />

thermal region based directly on experimental data, and a resonance region using the resonance parameter<br />

uncertainties from Atlas of Neutron Resonances. Scattering radius uncertainty is handled explicitly, and<br />

by using ENDF file 33 we bypass the possible file 32 processing issue which may lead to discrepancies<br />

between the multigroup covariances by the different processing codes.<br />

PR 77<br />

D-T Fusion Neutron Irradiations at AWE<br />

Matt Gardner, Andrew Simons, Ben Williams, Mike Rubery, AWE.<br />

A team at AWE has conducted a 2-year feasibility study to determine the suitability of ASP, its 300 keV<br />

deuteron accelerator, for the measurement of neutron-induced reaction cross-sections. Decay gammas resulting<br />

from 89Y(n,n’)89mY and 89Y(n,2n)88Y reactions have been collected using high-purity germanium<br />

and various different irradiation and counting geometries. Modelling of the ASP system and D-T interaction<br />

has been carried out using Geant4 in order to determine neutron spectra as a function of source-target<br />

angle and distance. Data collected using both analogue and list-mode systems have been analysed via<br />

parallel routes and the results compared. Fast extraction for short-lived products and low-background<br />

counting for long-lived products have both been employed; results from the data so collected are presented<br />

here.<br />

Corresponding author: Mark Cornock<br />

PR 78<br />

Commara-3.0 Covariance Library<br />

S. Hoblit, M. Herman, S. Mughabghab, A. Sonzogni, <strong>Brookhaven</strong> <strong>National</strong> <strong>Laboratory</strong>. G. Palmiotti, M.<br />

Salvatores, Argonne <strong>National</strong> <strong>Laboratory</strong>. P. Talou, M. Rising, M.B. Chadwick, G.M. Hale, A.C. Kahler,<br />

T. Kawano, R.C. Little, P.G. Young, Los Alamos <strong>National</strong> <strong>Laboratory</strong>.<br />

The Commara library is a set of covariances for the major reaction channels that are of importance to<br />

thermal and fast breeder reactors in addition to sensitivity studies. Version 3.0 will build upon the earlier<br />

work of version 2.0, released in March, 2011, which contained covariances for 110 materials in the AFCI<br />

33-group energy structure. The new version will refer to the central values of ENDF/B-VII.1, released<br />

December, 2011, and will incorporate covariances included in this release of the ENDF library, increasing<br />

the number of materials in Commara 3.0 to approximately 190. In addition to covariances for the 4-<br />

5 major reaction channels, version 3.0 will also expand the number of materials with covariances for<br />

prompt fission neutron spectra, mubar (P1 elastic) and nubar (average number of neutrons/fission), where<br />

available. Covariances for cross-reaction channels present in ENDF/B-VII.1 will also be included. The<br />

energy weighting will be modified from the pure 1/E weighting used with Commara 2.0 to 1/E + fission<br />

spectrum.<br />

PR 79<br />

301

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