Open Access
| Issue |
ND 2007
2007
|
|
|---|---|---|
| Article Number | 170 | |
| Number of page(s) | 4 | |
| Section | Thermal and resonance range | |
| DOI | https://doi.org/10.1051/ndata:07331 | |
| Published online | 17 June 2008 | |
International Conference on Nuclear Data for Science and Technology 2007
DOI: 10.1051/ndata:07331
Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6171, USA
LarsonNM@ornl.gov
Published online: 21 May 2008
© CEA 2008
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. ArbanasOak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6171, USA
LarsonNM@ornl.gov
Published online: 21 May 2008
Abstract
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