Development and testing of ENDF/B-VI.8 and ENDF/B-VII.0 coupled neutron-gamma libraries for SCALE 6 /

Bibliographic Details
Corporate Authors:	U.S. Nuclear Regulatory Commission. Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission. Division of Spent Fuel Storage and Transportation, Oak Ridge National Laboratory
Other Authors:	Wiarda, Dorothea
Format:	Government Document eBook
Language:	English
Published:	Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, [2009]
Subjects:	Criticality (Nuclear engineering) Nuclear power plants > United States > Shielding (Radiation) > Data processing. Nuclear power plants > United States > Shielding (Radiation) > Computer programs. Nuclear reactors > United States > Shielding (Radiation) > Data processing. Nuclear reactors > Shielding (Radiation) > United States > Computer programs. Neutron cross section standards > Databases. Neutron cross section standards > Computer programs.
Online Access:	https://purl.fdlp.gov/GPO/LPS121561

Description
Item Description:	Title from PDF title screen (viewed on Apr. 16, 2010). "Date published: February 2009." Performing organization: Oak Ridge National Laboratory. "NUREG/CR-6990." "ORNL/TM-2008/047." Electronic resource.
Physical Description:	1 online resource (140 pages) : illustrations (chiefly color)
Bibliography:	Includes bibliographical references (pages 89-90).