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

Publication Type
Conference Paper
Book Title
INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY, VOL 1, PROCEEDINGS
Publication Date
Page Numbers
641 to 644
Volume
1
Conference Name
International Conference on Nuclear Data for Science and Technology
Conference Location
Nice, France
Conference Sponsor
OECD Nuclear Energy Agency (NEA)
Conference Date
-

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.