Current Status of the R-Matrix Code SAMMY, with Emphasis on the Relationship to ENDF Formats

Conference · Tue Jan 01 00:00:00 EST 2008

OSTI ID:1081589

Larson, Nancy M ^[1]; Leal, Luiz C ^[1]; Sayer, Royce O ^[1]; Derrien, Herve ^[1]; Wiarda, Dorothea ^[1]; Arbanas, Goran ^[1]

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1. ORNL

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.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA)
• DOE Contract Number: DE-AC05-00OR22725
• OSTI ID: 1081589
• Resource Relation: Conference: International Conference on Nuclear Data for Science and Technology, Nice, France, 20070422, 20070427
• Country of Publication: United States
• Language: English