CSRL-V, processed ENDF/B-V 227-neutron-group and pointwise cross-section libraries for criticality safety, reactor and shielding studies / prepared by W.E. Ford III [and others] ; prepared for the Office of Nuclear Material Safety and Safeguards, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.

Bibliographic Details

Corporate Authors:	U.S. Nuclear Regulatory Commission. Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research Oak Ridge National Laboratory
Other Authors:	Ford, W. E. (Walter Edward), 1939-
Language:	English
Published:	Washington, D.C. : The Commission, 1982.
Subjects:	U.S. Nuclear Regulatory Commission. > Libraries. Overseas information libraries. Information storage and retrieval systems > Science.
Physical Description:	xi, 81 pages ; 28 cm + 2 microfiches.
Format:	Government Document Microfilm Book