Integrated System for Production of Neutronics and Photonics Calculational Constants. Volume 15, Part C. The LLL Evaluated Nuclear Data Library (ENDL): Translation of ENDL Neutron-Induced Interaction Data Into the ENDF/B Format
doi 10.2172/7184241
Full Text
Open PDFAbstract
Available in full text
Date
April 1, 1976
Authors
Publisher
Office of Scientific and Technical Information (OSTI)