Open Access
ND 2007
Article Number 170
Number of page(s) 4
Section Thermal and resonance range
Published online 17 June 2008
International Conference on Nuclear Data for Science and Technology 2007
DOI: 10.1051/ndata:07331

Current status of the R-Matrix code SAMMY, with emphasis on the relationship to ENDF formats

N.M. Larson, L.C. Leal, R.O. Sayer, H. Derrien, D. Wiarda and G. Arbanas

Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6171, USA

Published online: 21 May 2008

During the last decade, advances in evaluations of neutron-induced cross sections in the resolved resonance region have surpassed the ability of the Evaluated Nuclear Data Files (ENDF) to make use of those evaluations. At the higher energies used in new evaluations, effects that in the past were deemed to be negligible are now important. There is also a great demand for including uncertainty information in ENDF files. In this paper, we describe recently approved ENDF formats to accommodate new evaluations and their implementation in SAMMY. Other new features of the SAMMY code, available in the 2006 Revision 7 release, are also described.

© CEA 2008